copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Action Plan Committee Meeting
Used Fuel and High Level Waste
Date August 15 2016
2copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting Meeting Holder Rick Reid (rreidepricom)
Room Location Chamber 2 amp 4 (MSL)
Wednesday August 31 2016
Time Topic Lead
100 pm Welcome and Introductions T OrsquoConnor Xcel
115 pm Used Fuel Management Activities in Japan D Yamada TEPCO
130 pm Used Fuel and HLW Management Program Status Report Key developments in used fuel management Review of project prioritization results Proposed 2017-2018 portfolio
Z Martin TVA
230 pm Five-year plan Five-year plan Results of TAC strategic direction brainstorming
T OrsquoConnor Xcel R Reid EPRI
300 pm Afternoon Break All
330 pm Plans and risks High burnup data project Welded stainless steel dry storage canister aging
management plan Criticality and neutron absorber program
R Reid EPRI K Waldrop EPRI S Chu EPRI H Akkurt EPRI
415 pm Member Satisfaction Survey C Olexic EPRI
430 pm UFHLW Program APC messages for the Executive Council and Nuclear Power
Council T OrsquoConnor Xcel
500 pm Adjourn All
2copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting Meeting Holder Rick Reid (rreidepricom)
Room Location Chamber 2 amp 4 (MSL)
Wednesday August 31 2016
Time Topic Lead
100 pm Welcome and Introductions T OrsquoConnor Xcel
115 pm Used Fuel Management Activities in Japan D Yamada TEPCO
130 pm Used Fuel and HLW Management Program Status Report Key developments in used fuel management Review of project prioritization results Proposed 2017-2018 portfolio
Z Martin TVA
230 pm Five-year plan Five-year plan Results of TAC strategic direction brainstorming
T OrsquoConnor Xcel R Reid EPRI
300 pm Afternoon Break All
330 pm Plans and risks High burnup data project Welded stainless steel dry storage canister aging
management plan Criticality and neutron absorber program
R Reid EPRI K Waldrop EPRI S Chu EPRI H Akkurt EPRI
415 pm Member Satisfaction Survey C Olexic EPRI
430 pm UFHLW Program APC messages for the Executive Council and Nuclear Power
Council T OrsquoConnor Xcel
500 pm Adjourn All
copy 2016 Electric Power Research Institute Inc All rights reserved
Daichi YamadaEPRI Resident Researcher
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Used Fuel Management in Japan
Date 05 August 2016 Rev 0
PLACEHOLDER
4copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Zita MartinTechnical Advisory Committee Chair
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Technical Advisory Committee Meeting
Summary
Date 05 August 2016 Rev 0
DRAFT
6copy 2016 Electric Power Research Institute Inc All rights reserved
Topics
Meeting objectivesDevelopments in the used fuel topical areaReview of 2016 and 2017 fundingEPRI projects and prioritization resultsProposed 2017-2018 portfolio
7copy 2016 Electric Power Research Institute Inc All rights reserved
Meeting Objectives
Primary objective of the Technical Advisory Committee meeting was to review and reach consensus on the 2017-2018 research portfoliondash Projects to move forward based on prioritization and available fundingndash Discussion of basis for requests for funding of highest priority unfunded
work (strategic gap base reallocation emergent issues etc)Secondary objectives
ndash Begin development of 2019+ portfoliondash Identification of previously unidentified near-term critical issuesndash Important highlights of ongoing projects
8copy 2016 Electric Power Research Institute Inc All rights reserved
TAC August 2016 Meeting
XX attendees
XX Utilitiesndash XX USndash XX International
9copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (12)
NRC effort began to develop a graded approach to canister aging managementndash Greater emphasis on consequence of canister degradation (eg
CISCC flaws)Waste Control Specialists (WCS) submitted application for
centralized fuel storage in Aprilndash Eddy-LeaHoltec consortium expects to submit application this fallNRC Review of EPRI methodology and benchmarks for
PWR burn-up credit and NEI Criticality Guidance (NEI 12-16) continuesndash Responses provided for all Requests for Additional Information
10copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (22)
EPRI PWR reactivity decrement benchmarks approved for inclusion in International Reactor Physics Benchmark Evaluation Handbook by OEACDNEA NRC issued Generic Letter on neutron absorbers with
industry responses required in NovemberASME effort to develop Code Case for stainless steel
canister inspections is on goingNorth Anna sister rods shipped to Oak Ridge National
Laboratoryndash DOE Development of sister rod test plan continues
11copy 2016 Electric Power Research Institute Inc All rights reserved
Review of 2016 and 2017 FundingTotal does not include $156K
for Cask Loader Users GroupDOE funding
ndash 2016 $46Mndash 2017 $41M ndash 2018 $10MFunding for 2017 will be held
at the same levelndash Expect to continue this funding
level through 2019
Funding Type Amount(K$)
Base 3739Program Funders 428Strategic Gap 0Emerging Issues 0Total 4167
12copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results
13copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results Summary
24 of 32 utilities responded (75)ndash 18 of 23 US utilities (78)ndash 6 of 9 non-US utilities (67)ndash All ldquofleetrdquo utilities responded
Research Focus Area High Medium Low AverageAging Management of Dry Fuel Storage System Components 15 8 1 14
Used Fuel Cladding Performance during Extended Storage and Transportation 10 14 0 16
Criticality Control during Used Fuel Storage and Transportation 7 10 7 20
Technical Basis for Disposition of Used Nuclear Fuel 0 8 16 27
14copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results (percentage of respondents)
Aging Management of Dry Fuel
StorageComponents
Average 14 (High)
Used Fuel Cladding Performance
during Extended Storage and
Transportation
Average 16 (Medium)
Criticality Control during Storage
and Transportation
Average 20 (Medium)
Technical Basis for Disposition of
Used Nuclear Fuel
Average 27 (Low)
63
334
42
58
29
42
29 33
67
High Medium Low
15copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
4copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Zita MartinTechnical Advisory Committee Chair
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Technical Advisory Committee Meeting
Summary
Date 05 August 2016 Rev 0
DRAFT
6copy 2016 Electric Power Research Institute Inc All rights reserved
Topics
Meeting objectivesDevelopments in the used fuel topical areaReview of 2016 and 2017 fundingEPRI projects and prioritization resultsProposed 2017-2018 portfolio
7copy 2016 Electric Power Research Institute Inc All rights reserved
Meeting Objectives
Primary objective of the Technical Advisory Committee meeting was to review and reach consensus on the 2017-2018 research portfoliondash Projects to move forward based on prioritization and available fundingndash Discussion of basis for requests for funding of highest priority unfunded
work (strategic gap base reallocation emergent issues etc)Secondary objectives
ndash Begin development of 2019+ portfoliondash Identification of previously unidentified near-term critical issuesndash Important highlights of ongoing projects
8copy 2016 Electric Power Research Institute Inc All rights reserved
TAC August 2016 Meeting
XX attendees
XX Utilitiesndash XX USndash XX International
9copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (12)
NRC effort began to develop a graded approach to canister aging managementndash Greater emphasis on consequence of canister degradation (eg
CISCC flaws)Waste Control Specialists (WCS) submitted application for
centralized fuel storage in Aprilndash Eddy-LeaHoltec consortium expects to submit application this fallNRC Review of EPRI methodology and benchmarks for
PWR burn-up credit and NEI Criticality Guidance (NEI 12-16) continuesndash Responses provided for all Requests for Additional Information
10copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (22)
EPRI PWR reactivity decrement benchmarks approved for inclusion in International Reactor Physics Benchmark Evaluation Handbook by OEACDNEA NRC issued Generic Letter on neutron absorbers with
industry responses required in NovemberASME effort to develop Code Case for stainless steel
canister inspections is on goingNorth Anna sister rods shipped to Oak Ridge National
Laboratoryndash DOE Development of sister rod test plan continues
11copy 2016 Electric Power Research Institute Inc All rights reserved
Review of 2016 and 2017 FundingTotal does not include $156K
for Cask Loader Users GroupDOE funding
ndash 2016 $46Mndash 2017 $41M ndash 2018 $10MFunding for 2017 will be held
at the same levelndash Expect to continue this funding
level through 2019
Funding Type Amount(K$)
Base 3739Program Funders 428Strategic Gap 0Emerging Issues 0Total 4167
12copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results
13copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results Summary
24 of 32 utilities responded (75)ndash 18 of 23 US utilities (78)ndash 6 of 9 non-US utilities (67)ndash All ldquofleetrdquo utilities responded
Research Focus Area High Medium Low AverageAging Management of Dry Fuel Storage System Components 15 8 1 14
Used Fuel Cladding Performance during Extended Storage and Transportation 10 14 0 16
Criticality Control during Used Fuel Storage and Transportation 7 10 7 20
Technical Basis for Disposition of Used Nuclear Fuel 0 8 16 27
14copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results (percentage of respondents)
Aging Management of Dry Fuel
StorageComponents
Average 14 (High)
Used Fuel Cladding Performance
during Extended Storage and
Transportation
Average 16 (Medium)
Criticality Control during Storage
and Transportation
Average 20 (Medium)
Technical Basis for Disposition of
Used Nuclear Fuel
Average 27 (Low)
63
334
42
58
29
42
29 33
67
High Medium Low
15copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Zita MartinTechnical Advisory Committee Chair
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Technical Advisory Committee Meeting
Summary
Date 05 August 2016 Rev 0
DRAFT
6copy 2016 Electric Power Research Institute Inc All rights reserved
Topics
Meeting objectivesDevelopments in the used fuel topical areaReview of 2016 and 2017 fundingEPRI projects and prioritization resultsProposed 2017-2018 portfolio
7copy 2016 Electric Power Research Institute Inc All rights reserved
Meeting Objectives
Primary objective of the Technical Advisory Committee meeting was to review and reach consensus on the 2017-2018 research portfoliondash Projects to move forward based on prioritization and available fundingndash Discussion of basis for requests for funding of highest priority unfunded
work (strategic gap base reallocation emergent issues etc)Secondary objectives
ndash Begin development of 2019+ portfoliondash Identification of previously unidentified near-term critical issuesndash Important highlights of ongoing projects
8copy 2016 Electric Power Research Institute Inc All rights reserved
TAC August 2016 Meeting
XX attendees
XX Utilitiesndash XX USndash XX International
9copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (12)
NRC effort began to develop a graded approach to canister aging managementndash Greater emphasis on consequence of canister degradation (eg
CISCC flaws)Waste Control Specialists (WCS) submitted application for
centralized fuel storage in Aprilndash Eddy-LeaHoltec consortium expects to submit application this fallNRC Review of EPRI methodology and benchmarks for
PWR burn-up credit and NEI Criticality Guidance (NEI 12-16) continuesndash Responses provided for all Requests for Additional Information
10copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (22)
EPRI PWR reactivity decrement benchmarks approved for inclusion in International Reactor Physics Benchmark Evaluation Handbook by OEACDNEA NRC issued Generic Letter on neutron absorbers with
industry responses required in NovemberASME effort to develop Code Case for stainless steel
canister inspections is on goingNorth Anna sister rods shipped to Oak Ridge National
Laboratoryndash DOE Development of sister rod test plan continues
11copy 2016 Electric Power Research Institute Inc All rights reserved
Review of 2016 and 2017 FundingTotal does not include $156K
for Cask Loader Users GroupDOE funding
ndash 2016 $46Mndash 2017 $41M ndash 2018 $10MFunding for 2017 will be held
at the same levelndash Expect to continue this funding
level through 2019
Funding Type Amount(K$)
Base 3739Program Funders 428Strategic Gap 0Emerging Issues 0Total 4167
12copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results
13copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results Summary
24 of 32 utilities responded (75)ndash 18 of 23 US utilities (78)ndash 6 of 9 non-US utilities (67)ndash All ldquofleetrdquo utilities responded
Research Focus Area High Medium Low AverageAging Management of Dry Fuel Storage System Components 15 8 1 14
Used Fuel Cladding Performance during Extended Storage and Transportation 10 14 0 16
Criticality Control during Used Fuel Storage and Transportation 7 10 7 20
Technical Basis for Disposition of Used Nuclear Fuel 0 8 16 27
14copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results (percentage of respondents)
Aging Management of Dry Fuel
StorageComponents
Average 14 (High)
Used Fuel Cladding Performance
during Extended Storage and
Transportation
Average 16 (Medium)
Criticality Control during Storage
and Transportation
Average 20 (Medium)
Technical Basis for Disposition of
Used Nuclear Fuel
Average 27 (Low)
63
334
42
58
29
42
29 33
67
High Medium Low
15copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
6copy 2016 Electric Power Research Institute Inc All rights reserved
Topics
Meeting objectivesDevelopments in the used fuel topical areaReview of 2016 and 2017 fundingEPRI projects and prioritization resultsProposed 2017-2018 portfolio
7copy 2016 Electric Power Research Institute Inc All rights reserved
Meeting Objectives
Primary objective of the Technical Advisory Committee meeting was to review and reach consensus on the 2017-2018 research portfoliondash Projects to move forward based on prioritization and available fundingndash Discussion of basis for requests for funding of highest priority unfunded
work (strategic gap base reallocation emergent issues etc)Secondary objectives
ndash Begin development of 2019+ portfoliondash Identification of previously unidentified near-term critical issuesndash Important highlights of ongoing projects
8copy 2016 Electric Power Research Institute Inc All rights reserved
TAC August 2016 Meeting
XX attendees
XX Utilitiesndash XX USndash XX International
9copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (12)
NRC effort began to develop a graded approach to canister aging managementndash Greater emphasis on consequence of canister degradation (eg
CISCC flaws)Waste Control Specialists (WCS) submitted application for
centralized fuel storage in Aprilndash Eddy-LeaHoltec consortium expects to submit application this fallNRC Review of EPRI methodology and benchmarks for
PWR burn-up credit and NEI Criticality Guidance (NEI 12-16) continuesndash Responses provided for all Requests for Additional Information
10copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (22)
EPRI PWR reactivity decrement benchmarks approved for inclusion in International Reactor Physics Benchmark Evaluation Handbook by OEACDNEA NRC issued Generic Letter on neutron absorbers with
industry responses required in NovemberASME effort to develop Code Case for stainless steel
canister inspections is on goingNorth Anna sister rods shipped to Oak Ridge National
Laboratoryndash DOE Development of sister rod test plan continues
11copy 2016 Electric Power Research Institute Inc All rights reserved
Review of 2016 and 2017 FundingTotal does not include $156K
for Cask Loader Users GroupDOE funding
ndash 2016 $46Mndash 2017 $41M ndash 2018 $10MFunding for 2017 will be held
at the same levelndash Expect to continue this funding
level through 2019
Funding Type Amount(K$)
Base 3739Program Funders 428Strategic Gap 0Emerging Issues 0Total 4167
12copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results
13copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results Summary
24 of 32 utilities responded (75)ndash 18 of 23 US utilities (78)ndash 6 of 9 non-US utilities (67)ndash All ldquofleetrdquo utilities responded
Research Focus Area High Medium Low AverageAging Management of Dry Fuel Storage System Components 15 8 1 14
Used Fuel Cladding Performance during Extended Storage and Transportation 10 14 0 16
Criticality Control during Used Fuel Storage and Transportation 7 10 7 20
Technical Basis for Disposition of Used Nuclear Fuel 0 8 16 27
14copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results (percentage of respondents)
Aging Management of Dry Fuel
StorageComponents
Average 14 (High)
Used Fuel Cladding Performance
during Extended Storage and
Transportation
Average 16 (Medium)
Criticality Control during Storage
and Transportation
Average 20 (Medium)
Technical Basis for Disposition of
Used Nuclear Fuel
Average 27 (Low)
63
334
42
58
29
42
29 33
67
High Medium Low
15copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
7copy 2016 Electric Power Research Institute Inc All rights reserved
Meeting Objectives
Primary objective of the Technical Advisory Committee meeting was to review and reach consensus on the 2017-2018 research portfoliondash Projects to move forward based on prioritization and available fundingndash Discussion of basis for requests for funding of highest priority unfunded
work (strategic gap base reallocation emergent issues etc)Secondary objectives
ndash Begin development of 2019+ portfoliondash Identification of previously unidentified near-term critical issuesndash Important highlights of ongoing projects
8copy 2016 Electric Power Research Institute Inc All rights reserved
TAC August 2016 Meeting
XX attendees
XX Utilitiesndash XX USndash XX International
9copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (12)
NRC effort began to develop a graded approach to canister aging managementndash Greater emphasis on consequence of canister degradation (eg
CISCC flaws)Waste Control Specialists (WCS) submitted application for
centralized fuel storage in Aprilndash Eddy-LeaHoltec consortium expects to submit application this fallNRC Review of EPRI methodology and benchmarks for
PWR burn-up credit and NEI Criticality Guidance (NEI 12-16) continuesndash Responses provided for all Requests for Additional Information
10copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (22)
EPRI PWR reactivity decrement benchmarks approved for inclusion in International Reactor Physics Benchmark Evaluation Handbook by OEACDNEA NRC issued Generic Letter on neutron absorbers with
industry responses required in NovemberASME effort to develop Code Case for stainless steel
canister inspections is on goingNorth Anna sister rods shipped to Oak Ridge National
Laboratoryndash DOE Development of sister rod test plan continues
11copy 2016 Electric Power Research Institute Inc All rights reserved
Review of 2016 and 2017 FundingTotal does not include $156K
for Cask Loader Users GroupDOE funding
ndash 2016 $46Mndash 2017 $41M ndash 2018 $10MFunding for 2017 will be held
at the same levelndash Expect to continue this funding
level through 2019
Funding Type Amount(K$)
Base 3739Program Funders 428Strategic Gap 0Emerging Issues 0Total 4167
12copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results
13copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results Summary
24 of 32 utilities responded (75)ndash 18 of 23 US utilities (78)ndash 6 of 9 non-US utilities (67)ndash All ldquofleetrdquo utilities responded
Research Focus Area High Medium Low AverageAging Management of Dry Fuel Storage System Components 15 8 1 14
Used Fuel Cladding Performance during Extended Storage and Transportation 10 14 0 16
Criticality Control during Used Fuel Storage and Transportation 7 10 7 20
Technical Basis for Disposition of Used Nuclear Fuel 0 8 16 27
14copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results (percentage of respondents)
Aging Management of Dry Fuel
StorageComponents
Average 14 (High)
Used Fuel Cladding Performance
during Extended Storage and
Transportation
Average 16 (Medium)
Criticality Control during Storage
and Transportation
Average 20 (Medium)
Technical Basis for Disposition of
Used Nuclear Fuel
Average 27 (Low)
63
334
42
58
29
42
29 33
67
High Medium Low
15copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
8copy 2016 Electric Power Research Institute Inc All rights reserved
TAC August 2016 Meeting
XX attendees
XX Utilitiesndash XX USndash XX International
9copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (12)
NRC effort began to develop a graded approach to canister aging managementndash Greater emphasis on consequence of canister degradation (eg
CISCC flaws)Waste Control Specialists (WCS) submitted application for
centralized fuel storage in Aprilndash Eddy-LeaHoltec consortium expects to submit application this fallNRC Review of EPRI methodology and benchmarks for
PWR burn-up credit and NEI Criticality Guidance (NEI 12-16) continuesndash Responses provided for all Requests for Additional Information
10copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (22)
EPRI PWR reactivity decrement benchmarks approved for inclusion in International Reactor Physics Benchmark Evaluation Handbook by OEACDNEA NRC issued Generic Letter on neutron absorbers with
industry responses required in NovemberASME effort to develop Code Case for stainless steel
canister inspections is on goingNorth Anna sister rods shipped to Oak Ridge National
Laboratoryndash DOE Development of sister rod test plan continues
11copy 2016 Electric Power Research Institute Inc All rights reserved
Review of 2016 and 2017 FundingTotal does not include $156K
for Cask Loader Users GroupDOE funding
ndash 2016 $46Mndash 2017 $41M ndash 2018 $10MFunding for 2017 will be held
at the same levelndash Expect to continue this funding
level through 2019
Funding Type Amount(K$)
Base 3739Program Funders 428Strategic Gap 0Emerging Issues 0Total 4167
12copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results
13copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results Summary
24 of 32 utilities responded (75)ndash 18 of 23 US utilities (78)ndash 6 of 9 non-US utilities (67)ndash All ldquofleetrdquo utilities responded
Research Focus Area High Medium Low AverageAging Management of Dry Fuel Storage System Components 15 8 1 14
Used Fuel Cladding Performance during Extended Storage and Transportation 10 14 0 16
Criticality Control during Used Fuel Storage and Transportation 7 10 7 20
Technical Basis for Disposition of Used Nuclear Fuel 0 8 16 27
14copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results (percentage of respondents)
Aging Management of Dry Fuel
StorageComponents
Average 14 (High)
Used Fuel Cladding Performance
during Extended Storage and
Transportation
Average 16 (Medium)
Criticality Control during Storage
and Transportation
Average 20 (Medium)
Technical Basis for Disposition of
Used Nuclear Fuel
Average 27 (Low)
63
334
42
58
29
42
29 33
67
High Medium Low
15copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
9copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (12)
NRC effort began to develop a graded approach to canister aging managementndash Greater emphasis on consequence of canister degradation (eg
CISCC flaws)Waste Control Specialists (WCS) submitted application for
centralized fuel storage in Aprilndash Eddy-LeaHoltec consortium expects to submit application this fallNRC Review of EPRI methodology and benchmarks for
PWR burn-up credit and NEI Criticality Guidance (NEI 12-16) continuesndash Responses provided for all Requests for Additional Information
10copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (22)
EPRI PWR reactivity decrement benchmarks approved for inclusion in International Reactor Physics Benchmark Evaluation Handbook by OEACDNEA NRC issued Generic Letter on neutron absorbers with
industry responses required in NovemberASME effort to develop Code Case for stainless steel
canister inspections is on goingNorth Anna sister rods shipped to Oak Ridge National
Laboratoryndash DOE Development of sister rod test plan continues
11copy 2016 Electric Power Research Institute Inc All rights reserved
Review of 2016 and 2017 FundingTotal does not include $156K
for Cask Loader Users GroupDOE funding
ndash 2016 $46Mndash 2017 $41M ndash 2018 $10MFunding for 2017 will be held
at the same levelndash Expect to continue this funding
level through 2019
Funding Type Amount(K$)
Base 3739Program Funders 428Strategic Gap 0Emerging Issues 0Total 4167
12copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results
13copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results Summary
24 of 32 utilities responded (75)ndash 18 of 23 US utilities (78)ndash 6 of 9 non-US utilities (67)ndash All ldquofleetrdquo utilities responded
Research Focus Area High Medium Low AverageAging Management of Dry Fuel Storage System Components 15 8 1 14
Used Fuel Cladding Performance during Extended Storage and Transportation 10 14 0 16
Criticality Control during Used Fuel Storage and Transportation 7 10 7 20
Technical Basis for Disposition of Used Nuclear Fuel 0 8 16 27
14copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results (percentage of respondents)
Aging Management of Dry Fuel
StorageComponents
Average 14 (High)
Used Fuel Cladding Performance
during Extended Storage and
Transportation
Average 16 (Medium)
Criticality Control during Storage
and Transportation
Average 20 (Medium)
Technical Basis for Disposition of
Used Nuclear Fuel
Average 27 (Low)
63
334
42
58
29
42
29 33
67
High Medium Low
15copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
10copy 2016 Electric Power Research Institute Inc All rights reserved
Key Developments in the Used Fuel Topical Area (22)
EPRI PWR reactivity decrement benchmarks approved for inclusion in International Reactor Physics Benchmark Evaluation Handbook by OEACDNEA NRC issued Generic Letter on neutron absorbers with
industry responses required in NovemberASME effort to develop Code Case for stainless steel
canister inspections is on goingNorth Anna sister rods shipped to Oak Ridge National
Laboratoryndash DOE Development of sister rod test plan continues
11copy 2016 Electric Power Research Institute Inc All rights reserved
Review of 2016 and 2017 FundingTotal does not include $156K
for Cask Loader Users GroupDOE funding
ndash 2016 $46Mndash 2017 $41M ndash 2018 $10MFunding for 2017 will be held
at the same levelndash Expect to continue this funding
level through 2019
Funding Type Amount(K$)
Base 3739Program Funders 428Strategic Gap 0Emerging Issues 0Total 4167
12copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results
13copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results Summary
24 of 32 utilities responded (75)ndash 18 of 23 US utilities (78)ndash 6 of 9 non-US utilities (67)ndash All ldquofleetrdquo utilities responded
Research Focus Area High Medium Low AverageAging Management of Dry Fuel Storage System Components 15 8 1 14
Used Fuel Cladding Performance during Extended Storage and Transportation 10 14 0 16
Criticality Control during Used Fuel Storage and Transportation 7 10 7 20
Technical Basis for Disposition of Used Nuclear Fuel 0 8 16 27
14copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results (percentage of respondents)
Aging Management of Dry Fuel
StorageComponents
Average 14 (High)
Used Fuel Cladding Performance
during Extended Storage and
Transportation
Average 16 (Medium)
Criticality Control during Storage
and Transportation
Average 20 (Medium)
Technical Basis for Disposition of
Used Nuclear Fuel
Average 27 (Low)
63
334
42
58
29
42
29 33
67
High Medium Low
15copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
11copy 2016 Electric Power Research Institute Inc All rights reserved
Review of 2016 and 2017 FundingTotal does not include $156K
for Cask Loader Users GroupDOE funding
ndash 2016 $46Mndash 2017 $41M ndash 2018 $10MFunding for 2017 will be held
at the same levelndash Expect to continue this funding
level through 2019
Funding Type Amount(K$)
Base 3739Program Funders 428Strategic Gap 0Emerging Issues 0Total 4167
12copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results
13copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results Summary
24 of 32 utilities responded (75)ndash 18 of 23 US utilities (78)ndash 6 of 9 non-US utilities (67)ndash All ldquofleetrdquo utilities responded
Research Focus Area High Medium Low AverageAging Management of Dry Fuel Storage System Components 15 8 1 14
Used Fuel Cladding Performance during Extended Storage and Transportation 10 14 0 16
Criticality Control during Used Fuel Storage and Transportation 7 10 7 20
Technical Basis for Disposition of Used Nuclear Fuel 0 8 16 27
14copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results (percentage of respondents)
Aging Management of Dry Fuel
StorageComponents
Average 14 (High)
Used Fuel Cladding Performance
during Extended Storage and
Transportation
Average 16 (Medium)
Criticality Control during Storage
and Transportation
Average 20 (Medium)
Technical Basis for Disposition of
Used Nuclear Fuel
Average 27 (Low)
63
334
42
58
29
42
29 33
67
High Medium Low
15copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
12copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results
13copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results Summary
24 of 32 utilities responded (75)ndash 18 of 23 US utilities (78)ndash 6 of 9 non-US utilities (67)ndash All ldquofleetrdquo utilities responded
Research Focus Area High Medium Low AverageAging Management of Dry Fuel Storage System Components 15 8 1 14
Used Fuel Cladding Performance during Extended Storage and Transportation 10 14 0 16
Criticality Control during Used Fuel Storage and Transportation 7 10 7 20
Technical Basis for Disposition of Used Nuclear Fuel 0 8 16 27
14copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results (percentage of respondents)
Aging Management of Dry Fuel
StorageComponents
Average 14 (High)
Used Fuel Cladding Performance
during Extended Storage and
Transportation
Average 16 (Medium)
Criticality Control during Storage
and Transportation
Average 20 (Medium)
Technical Basis for Disposition of
Used Nuclear Fuel
Average 27 (Low)
63
334
42
58
29
42
29 33
67
High Medium Low
15copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
13copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results Summary
24 of 32 utilities responded (75)ndash 18 of 23 US utilities (78)ndash 6 of 9 non-US utilities (67)ndash All ldquofleetrdquo utilities responded
Research Focus Area High Medium Low AverageAging Management of Dry Fuel Storage System Components 15 8 1 14
Used Fuel Cladding Performance during Extended Storage and Transportation 10 14 0 16
Criticality Control during Used Fuel Storage and Transportation 7 10 7 20
Technical Basis for Disposition of Used Nuclear Fuel 0 8 16 27
14copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results (percentage of respondents)
Aging Management of Dry Fuel
StorageComponents
Average 14 (High)
Used Fuel Cladding Performance
during Extended Storage and
Transportation
Average 16 (Medium)
Criticality Control during Storage
and Transportation
Average 20 (Medium)
Technical Basis for Disposition of
Used Nuclear Fuel
Average 27 (Low)
63
334
42
58
29
42
29 33
67
High Medium Low
15copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
14copy 2016 Electric Power Research Institute Inc All rights reserved
Prioritization Results (percentage of respondents)
Aging Management of Dry Fuel
StorageComponents
Average 14 (High)
Used Fuel Cladding Performance
during Extended Storage and
Transportation
Average 16 (Medium)
Criticality Control during Storage
and Transportation
Average 20 (Medium)
Technical Basis for Disposition of
Used Nuclear Fuel
Average 27 (Low)
63
334
42
58
29
42
29 33
67
High Medium Low
15copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
15copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
16copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Aging Management
of DSCC
Canister Aging Management
(2017-2021)
Advanced NDE (2017-2021)
Repair and Mitigation
(2017-2020)
Consequence Analysis
(2017-2018)
High Priority
Mean = 140
Median = 1
Sample Feedback The Consequence Analysis work and the SS canister aging
management work are of highest priority for the industry to be able to influence NRCs Risk Informed approach to aging management of dry cask systems
Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks Work on cask seals would be high priority
Stainless steel canister NDE and delivery systems should have the highest priority within this RFA
I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions Also work on repair techniques for cracks if discovered would also be helpful
Portfolio Recommendations
Fund continuing projects
Fund consequence analysis
Delay work on repair and mitigation pending efforts by the ESCP subcommittee and vendors
Funded Unfunded
63
334
High Medium Low
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
17copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
18copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Used Fuel Integrity
High Burnup Data Project
(2017+)
Cladding Performance
(2017+) Medium Priority
Mean = 16
Sample Feedback The high burnup project is currently the industrys highest
priority Project High Burnup Demo is high priority High Burnup Issues
Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior
after hydride reorientation when the maximum temperature achieved during drying is lower than 400ordmC (for example 350ordmC)
The use of a modified loaded MPC canister with various fuel types and analysis of the high burn-up fuel rods to determine effects will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRIDOE agreement this should be funded
Portfolio Recommendations
Fund both continuing projects
Funded Work Unfunded
High Medium Low
42
58
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
19copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
20copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage
Criticality Control during
Used Fuel Storage
PWR Reactivity Depletion
(2011-2017)
BWR Reactivity Depletion
(2017-2019)
Neutron Absorber Handbook
(2017-2018)
Neutron Absorber
Degradation(2017+)
Medium Priority
Mean = 20
Sample Feedback With the increased focus by the NRC on neutron absorber aging
the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs In addition the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained
Medium priority for the project Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation Low priority for the other projects
For plants with no Boral coupons installed in their SFP (or dry canisters) it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data Zion test data etc
Portfolio Recommendations
Fund all continuing projects
Delay revision of the Neutron Absorber Handbook to 2019 or 2020
Funded Work Unfunded
High Medium Low
29
42
29
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
21copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
22copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Technical Basis for
Disposal of Used Nuclear
Fuel
Low Priority
Mean = 270
Sample Feedback Medium priority for the project Technical input to risk
assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities Low priority for the rest of the work
Near term focus should be on transportation and long-term storage at CIS facilities
While this will eventually become important it is not a critical issue of today and there is time to deal with this
Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts
Portfolio Recommendations
NA
Funded Work Unfunded
High Medium Low
33
67
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
23copy 2016 Electric Power Research Institute Inc All rights reserved
Proposed 2017-2018 Portfolio
Project Name Year2017 2018
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister Repair and mitigation techniquesoptions 0 0
RFA Total 1250 975RFA Used Fuel Cladding Performance during Extended Storage and
TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution ndash Cladding Performance 400 400
RFA Total 1687 1862RFA Criticality Control during Used Fuel Storage and Transportation
PWR Reactivity Depletion - EPRI Methodology 150 0BWR Reactivity Depletion - EPRI Methodology 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0
RFA Total 980 1080Unassociated Projects
Extended Storage Collaboration Program 250 250
CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167
Fund All Continuing
Projects
3 New Projects Not
FundedRed ndash Not Funded
Black - Funded
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
24copy 2016 Electric Power Research Institute Inc All rights reserved
Unfunded Projects
Canister Repair and Mitigationndash Manage through ESCP subcommitteendash Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision
ndash Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study
ndash Verify need for the effort and seek alternative funding if warranted
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
25copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
26copy 2016 Electric Power Research Institute Inc All rights reserved
Back-Up SlidesProject Summaries
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
27copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
28copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management
Issuendash Chloride-Induced Stress Corrosion Cracking (CISCC) is a
potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activitiesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
29copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
30copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue
ndash Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation
ndash Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented
ndash Demonstration of low consequences could provide justification for reducedeliminated inspections during extended storage
Key activitiesndash Utilize results and recommendations from 2016 scoping study to develop one or more
generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
31copy 2016 Electric Power Research Institute Inc All rights reserved
MitigationRepair of Welded Stainless Steel CanistersNew Project ndash Not Funded Issue
ndash Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments
ndash Industry is lacking qualified techniques for mitigation and repair following any ldquounacceptablerdquo inspection finding
Key activitiesndash Evaluate techniques that have been applied for mitigation and repair of
operating components that are susceptible to PWSCC for application to welded canisters
ndash Investigate technologies that may be uniquely applicable to canistersndash Provide recommendations for further efforts to develop and demonstrate viable
techniques Value
ndash Provides a starting point for development of canister-specific repair and mitigation techniques leveraging previous work on reactor components
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
32copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
33copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
34copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activitiesndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
35copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
36copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
37copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
38copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber MaterialsNew Project Update of Neutron Absorber Material Handbook ndash Not FundedNeutron Absorber Handbook published in 2009
ndash Since then there have been many changes in material development operational experience regulatory perspectives
Objective Update Neutron Absorber Material Handbook Scope and Approach Review the handbook and
Revise the content as needed Include new developments in
ndash Neutron absorber materials ndash Operational experiencendash Regulatory perspectives
Anticipated Deliverable Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value
ndash Provides an up-to-date resource on neutron absorber materials
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
39copy 2016 Electric Power Research Institute Inc All rights reserved
Technical Basis for Disposal of Used Nuclear Fuel
Project types Typical deliverables Specific near-term activities
bull Technical evaluations bull Technical reportsbull No near-term activities
No current work Future work might include technical basis for disposal andor long-term management
plans being considered in member countriesndash Assistance with performance and risk assessmentsndash Input to environmental impact assessmentsndash Technical input to risk assessments associated with transportation of fuel for long-
term storage at centralized interim storage facilities
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
40copy 2016 Electric Power Research Institute Inc All rights reserved
Projects not Associated to a RFA
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
41copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
42copy 2016 Electric Power Research Institute Inc All rights reserved
CFD Study of Partial SFP Drain DownNew Project ndash Not Funded Issue
ndash A partial drain down scenario may be the most limiting with respect to the potential for a ldquozirconium firerdquo This scenario has not been fully evaluated Due to the lack of this evaluation plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced
Key Activitiesndash A computational fluid dynamics study of the partial spent fuel pool drain down
scenario will be performed to determine the conditions under which a zirconium fire could occur
ndash This study will include a number of drain down levels and for each level will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000degC 1832degF) as a function of fuel cooling time
Valuendash Potential reduction in the time after shutdown that full emergency response must be
maintained
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Rick ReidProgram Manager
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Five-Year Plan2017-2021
Date 05 August 2016 Rev 0
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
44copy 2016 Electric Power Research Institute Inc All rights reserved
Five-Year Plan 2017-2021Project Name 2017 2018 2019 2020 2021
RFA Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management
SS canister Advanced NDE and Delivery systems
Canister Consequence Analysis
SS canister prevention and mitigation techniquesoptions
RFA Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project
High Burnup Issues Resolution ndash Cladding Performance
RFA Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - EPRI Methodology
BWR Reactivity Depletion - EPRI Methodology
Neutron Absorber Material Degradation
Neutron Absorber Handbook
Unassigned ProjectsExtended Storage Collaboration Program
New Projects 778K 1057K 24M
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
45copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (12)
Technical bases for ndash Long-term storage aging management plansndash Transportation after long-term storage On-going activities
ndash 2017 Finalize stainless steel canister aging management guidance follow ASME code case development
ndash 2017-2018 Complete consequence analysisndash 2017-2021 Complete development and deploy NDE techniquesndash 2013-2019 High burn up demonstrationndash Continuing High burnup fuel - cladding performance
Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
46copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Goals and Trajectory (22)
Potential near-term activities (2017 ndash 2021)ndash concrete over pack aging management guidancendash stainless steel canister degradation mitigation and repair options
and design and loading considerationsndash high burn-up demonstration support for transport licensing Longer-term activities
ndash continue Extended Storage Collaboration Programndash high burn-up demonstration long-term data collection followed by
cask reopening
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
47copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Goals and Trajectory Technical bases for
ndash PWR spent fuel pool criticality calculation ndash Neutron absorber material aging managementndash BWR spent fuel pool criticality calculation
Current and near-term activitiesndash 2013-2018 Boral coupon accelerated corrosion testingndash 2015-2016 NRC acceptance of PWR SFP criticality methodologyndash 2015-2017 Zion coupon measurements and panel harvestingndash 2016-2019 BWR SFP criticality methodologyndash 2017-2019 Enhanced monitoring techniquesndash 2020 Neutron Absorber Handbook revision
Longer-term and continuing activities Neutron Absorber Users Group
Maintain Maximum Spent Fuel Pool Storage Flexibility
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
48copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (12)
Geological disposal evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage experience summary and evaluation of
technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision last updated in 2011Hydride Reorientation report providing a summary of research
efforts to close out this issueAging Management of Bolted Cask Seals initial analysis to
determine technical issues ISFSI Security review technical basis work being developed by US
DOE
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
49copy 2016 Electric Power Research Institute Inc All rights reserved
Other Potential Near-Term ProjectsProject Areas (22)
License Renewal Guidance focus on implementation activitiesTransportation of Used Fuel technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel
evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database repository of industry
data on the results of coupon analysesSpent Fuel Pool water chemistry control technical basis for
water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses technical analysis of
credible postulated spent fuel pool accidents
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
50copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
Project Plans and Risks
Date 05 August 2016 Rev 0
Keith Waldrop
Principal Technical Leader
Rick Reid
Program Manager
Shannon Chu
Senior Technical Leader
Hatice Akkurt
Principal Technical Leader
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
52copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management of Dry Fuel Storage System Components
Project types Typical deliverables Specific near-term activities
bull Guidance development bull Guidance documentsbull Training workshops bull Stainless steel canister aging management guidance
bull Technical basis development bull Technical reports bull Consequence analysis for CISCC in stainless steel canisters
bull Inspection method development bull Technical reportsbull Demonstrations
bull Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems
Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel
canisters Other issues could include degradation of seals in bolted metal cask designs or
degradation of concrete over packs in canister-based systems Work includes failure modes evaluation development of aging management guidance
development of inspection techniques development of mitigation and repair techniques etc
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
53copy 2016 Electric Power Research Institute Inc All rights reserved
Welded Stainless Steel Canister Aging Management Issue
ndash CISCC is a potential degradation mechanism for used fuel storage canisters in dry cask storage systems license renewal activities have been impacted with requirements to address this issue in learning aging management programs
Key activities for 2016-2018ndash Complete Aging Management Guidelinesndash Provide implementation training for aging management
guidance ndash Support ASME Task Group on In‐service Inspection of Spent
Fuel Storage and Transportation Containments
Valuendash Provide guidance on actions necessary to support risk-
informed aging management of stainless steel canisters
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
54copy 2016 Electric Power Research Institute Inc All rights reserved
Aging Management Guideline Development Schedule Draft A (not including App C) advisory panel review period July 15
ndash August 15 Draft B advisory panel review period September 2016 Draft C advisory panel + TAC review period mid-October ndash mid-
November 2016 Distribute DRAFT C comment resolution and conduct EPRI quality
program review of final report December 2016 Aging Management Guidance to Address Potential Chloride-
Induced Stress Corrosion Cracking (CISCC) of Welded Stainless Steel Canisters 3002008193 early 2017
Continuing project in 2017-2019+ to provide implementation training and support and to facilitate incorporation into ASME Code Case
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
55copy 2016 Electric Power Research Institute Inc All rights reserved
Project Area Challenges
Must remain engaged in ASME Code Case development effort to ensure EPRI program technical basis work is accurately consideredincorporatedMust ensure collaboration continues in the development of
adequate inspection techniques to support aging managementndash Slow crack growth rate provides margin for careful evaluation of
mitigation and repair options
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
56copy 2016 Electric Power Research Institute Inc All rights reserved
Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue
ndash Due to potential for degradation inspection of storage canisters may be required
ndash Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems
Key activitiesndash Continue development and mock-up testing of promising
NDE techniquesndash Continue development of delivery systemsndash Continue system refinement and demonstration on empty
canisters ndash Conduct demonstration on a loaded canister
Valuendash Develop new technology needed to conduct required
inspections
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
57copy 2016 Electric Power Research Institute Inc All rights reserved
McGuire Demonstration - May 16 2016 Canister Magnastor (empty) Able to access multiple locations within
the cask ROV carried visual and thermal
cameras and radiation monitor Lessons learned on cable
management cables caught on internal support a wheel came off of the ROV and was recovered ROV modified with secondary
mechanism for wheel attachment and additional standoffs to avoid repeat of issues
Tech Transfer NominationsSubmitted for Utility Hosts
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
58copy 2016 Electric Power Research Institute Inc All rights reserved
Maine Yankee Demonstration ndash July 11 2016 Canister Greater than class C waste (first time exposing ROV to radiation) Utilized magnetic ROV to carry and manipulate camera and dosimetry and to collect surface
samples Visual examination of the surface ndash able to get access to greater than 75 of canister outer surface Measured radiation doses in all 4 vents and from top to bottom along the canister axis in line with 3
of 4 vents Thermal camera recorded images Collected 8 surface samples 6 on the inlet vent shelf 2 on the shield plug surface which were sent
to Sandia for analysis
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
59copy 2016 Electric Power Research Institute Inc All rights reserved
Deliverables Dry Canister Storage System Inspection and Robotic Delivery
System Development 3002008234 May 2016 Nondestructive Evaluation Investigation of Acoustic Emission
Technologies for Monitoring Inaccessible Regions of Dry Fuel Storage Systems 3002007816 June 2016 (NDE program funding) Eddy Current Array Study 3002007801 pending 2016 (NDE
program funding)
Continuing project in 2017-2018+ to further refine and demonstrate ability of ROV in combination with NDE to inspect loaded spent fuel canisters (vertical and horizontal configurations) Work in 2019+ to inspect additional designs and transition technology to commercial deployment
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
60copy 2016 Electric Power Research Institute Inc All rights reserved
Through-wall CISCC Consequence Analysis
Issuendash Regulators are beginning to develop risk-informed regulatory approach to used fuel
storage and transportationndash Actual consequences of a through-wall CISCC flaw are expected to be very low but
have not been fully analyzed and documentedndash Demonstration of low consequences could provide justification for reducedeliminated
inspections during extended storage Key activities for 2016-2018
ndash Utilize results and recommendations from 2016 scoping study to develop one or more generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years
ndash Interact with NRCACRSNEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach
Valuendash Develop technical basis for risk-informed canister aging management
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
61copy 2016 Electric Power Research Institute Inc All rights reserved
Status of 2016 Effort
More than 20 references have been identified for evaluationReport publication in early 2017
ndash Dry Cask Storage Welded Stainless Steel Canister Breach Consequence Analysis Scoping Study 3002008192
Continuing project in 2017-2018 to conduct recommended analysis and comparisons
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
62copy 2016 Electric Power Research Institute Inc All rights reserved
Used Fuel Integrity during Extended Storage and Transportation
Project types Typical deliverables Specific near-term activitiesbull Testing and evaluation of used
fuel during storage bull Technical reports bull High burnup fuel confirmatory data project
bull Fundamental RampD on the effect of irradiation on fuel cladding materials
bull Technical reportsbull Collaborative test programs to determine the effect
of irradiation on cladding performance in high burnup fuel
Current focus is understanding material properties of cladding materials in high burnup fuelndash Properties may change during storagendash Critical to determination of performance under normal and accident loads that may
occur during transportationndash The potential for hydride reorientation is a principal concern
Generation of data to predict the performance of differing cladding types is a key element in the research focus areandash Data on advanced cladding materials ideally available prior to transfer to dry storage
but must be available prior to transport
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
63copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue
ndash Lack of data on high burnup fuel under dry storage conditionsndash Conduct a full scale long term research project to determine the effect of dry storage
on high burnup cladding under typical conditions Key Activities for 2016-2018
ndash Complete fabrication of the cask and instrumentationndash Load the caskndash Collect data (temperatures gas composition)
Valuendash Provides confirmatory data to show that high burnup fuel may be safely stored and
transportedndash Supports industry license renewal commitments (US)
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
64copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Licensing
TN-32 cask not currently licensed for high burnup fuel or transportationndash Very similar design to TN-40 which is licensed for storage of HBU
fuel and transport of low burnup fuelndash Site specific license limited to specific HBU fuel to be loadedndash Performing some key calculations for transportation earlyStarting the Demo in 2017 depends on 18 month NRC review
ndash Despite 2nd round of RAIs anticipate LAR approval ahead of schedule
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
65copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Fuel SelectionDesire peak cladding temperatures near 400degC limit
ndash Licensing model must be lt 400degC Other material thermal limits must be metndash Difficulty getting clad temperatures above 300degCndash Altered loading pattern to keep high priority assemblies with fillers of high heat (16 kW)ndash Resultant peak clad temperatures estimated ~ 320degC (TN calculated 350degC)ndash Total cask heat load now 37 kW 327 current license limit
Fuel selection finalized 10-16-14PNNL reran model using ORIGEN calculated best estimate decay heat
ndash Total decay heat from 369 kW to 306 kW Peak clad temperature from 320degC to 271degC ndash Not planning to modify HBU demo fuel loadingndash PNNL plans to do additional analysis for other systems loaded with high heat load
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
66copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges Gas Sampling Gas sampling on pad potential for unmonitored release
ndash Approach proposed for sampling on pad Place temporary enclosure over cask Remove vent port cover and take sample Replace vent port cover with new seal He sniff test instead of normal He leak rate test Cannot meet initial leak rate test criteria Continue overpressure system monitoring
ndash Not included in initial submittal Avoid impacting loading schedule
ndash Dominion working with NRC on appropriate strategy and timing
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
67copy 2016 Electric Power Research Institute Inc All rights reserved
HBU Demo Project Challenges ProjectPolitical Risks
Fuel Examination Facilityndash Large hot cell needed to open cask dryndash No facility currently existsndash Sustained funding and political support needed to complete a
facility in 10 yearsndash INL is DOErsquos lead lab (preferred location) but current political
landscape not supportivendash DOE exploring options
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
68copy 2016 Electric Power Research Institute Inc All rights reserved
High Burnup Issues Resolution ndash Cladding Performance
Issuendash Data on ldquoadvancedrdquo claddings (ZirloTM Optimized ZirloTM M5 AXIOM etc) are
needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions
Key Activities for 2016-2018ndash Examinations of high-burnup fuel in hot cells through active collaborations with EDF RampD Nuclear Fuel Industry Research (NFIR) Group
Valuendash Leverages global RampD on high burnup cladding propertiesndash Forms continuing technical basis for the safe storage and transportation of high
burnup fuel using advanced cladding materialsndash Provides early identification of any cladding-type specific issues
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
69copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality Control during Used Fuel Storage Work in this research focus area includes
ndash Evaluation of long-term performance of neutron absorbing materialsndash Improvement of computational models used to determine criticality safety marginsndash Experimentally derived benchmarks for assessing the bias and uncertainty of
computational modelndash Development of in-situ and ex-situ test methods for evaluating the performance of
neutron absorbing materials
Project types Typical deliverables Specific near-term activities
bull Material testing bull Technical reportsbull Zion comparative analysis projectbull Accelerated corrosion testing of Boral specimens
bull Guidance and benchmarking bull Technical reports
bull PWR and BWR reactivity depletion benchmarks
bull Users group bull Meetings and webcasts bull Neutron Absorbers Users Group
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
70copy 2016 Electric Power Research Institute Inc All rights reserved
Spent Fuel Pool Criticality Depletion Benchmarks for Full Burnup Credit Validation Issue and Background
ndash 2010 regulatory guidance reduced reactivity decrement due to fuel burnupndash EPRI methodology and benchmarks and associated NEI Criticality Guidance (NEI 12-16)
under review by US NRC Key Activities
ndash Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents
ndash For BWR benchmarks conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders including utilities and regulators Perform the development of benchmarks pending on feedback
Valuendash Provides technical basis and approach for reduced uncertainty in the reactivity decrement
ultimately preserving SFP criticality margins and loading capability
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
71copy 2016 Electric Power Research Institute Inc All rights reserved
SFP Criticality Project Area Issues bull The review includes work spanning over 6 years (EPRI benchmarks)
bull Since it includes multi-components review and response to RAIs can be challenging
bull Continued support is needed to finalize this important work for the industry and get NRC endorsement to
bull Simplify application process with better consistency
bull Avoid loss of storage space in SFPs
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
72copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Material Degradation Issue
ndash Current materials may be prone to degradation RampD needed to identify and characterize degradation modes quantify the effect of degradation on material performance and develop monitoring and aging management programs
Key activities (Ongoing projects)ndash Accelerated corrosion test remove and evaluate fourth-year coupons compare to
results from previous yearsndash Zion project complete analysis of coupons in-situ measurements and specimens
from harvested panels and publish the final report that compares results from these three measurements
ndash Neutron Absorbers Users Group conduct annual meeting (July 2017) Key activities (New project)
ndash Development of alternative neutron absorber material monitoring approach Value
ndash Provides the technical basis for aging management of neutron absorber materials
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
73copy 2016 Electric Power Research Institute Inc All rights reserved
Zion Comparative Analysis Summarybull Panels are in very good condition Very good agreement between panel and
coupon areal density valuesbull Coupon Analysis complete Panel and BADGER analysis ongoing bull Reasons behind discrepancies between BADGER and panel results are not
clear yetbull Several EPRI reports are under preparation
bull Coupon and panel analysis reports will be published in 2016 bull BADGER and final report comparing panel vs coupon vs BADGER
measurements will be published in 2017
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
74copy 2016 Electric Power Research Institute Inc All rights reserved
Accelerated Corrosion Test Summary
bull Year 1-3 results did not show any significant degradationbull Areal density values are in excellent agreement with pre-characterized
valuesbull The most significant key result is for the clad removed coupons which
showed no statistically significant change in areal density after 2 year at elevated temperatures
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
75copy 2016 Electric Power Research Institute Inc All rights reserved
Criticality RFA ndash 2016 amp Beyond
2016 2017 2018 and beyond
CISCC Susceptibility Assessment Criteria
Aging Management Guidance
Canister Mitigation and Repair Technology
Flaw Growth amp Flaw Tolerance
Assessment
Zion Comparative Analysis Project
Criticality RFA Projects
Evaluation of Impact of Blister amp Pits on Reactivity
Nondestructive Examination Techniques amp Delivery System Development
Evaluation of Impact of Blister amp Pit on
Reactivity
Zion Comparative Analysis Project
Accelerated Corrosion Test Project
Development of Alternative Neutron Absorber Monitoring Approaches
Review of EPRI Benchmarks amp NEI 12-16
Publication of revised EPRI Benchmark amp Utilization reports amp Sensitivity report
BWR Burnup Credit
Neutron Absorber User Group (NAUG)
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
76copy 2016 Electric Power Research Institute Inc All rights reserved
Neutron Absorber Projects ndash 2016 PublicationsPresentations
bull Presentation on Overview of EPRI RampD on Neutron Absorber Materialsbull Presented at NEI UFMC May 2016
bull Presentation on Zion Projectbull Presented at International LWR MRP August 2016
bull ANS Papers amp Summariesbull Zion Panel results ANS Winter November 2016bull Accelerated Corrosion results ANS Winter November 2016
bull Invited to organize a session on neutron absorber materials at ANS Summer meeting June 2017 San Francisco CA
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
77copy 2016 Electric Power Research Institute Inc All rights reserved
Project not Associated to a RFA
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
78copy 2016 Electric Power Research Institute Inc All rights reserved
Extended Storage Collaboration Program (ESCP)
Key Activities and Anticipated Deliverablesndash One day ESCP meeting in May and 3-day meeting in DecemberWhen possible conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference
ndash Publication of International Data Gap reportndash Work on NDE Subcommittee reportndash Participation in global industry group meetingsValue
ndash Allows leveraging of global work being performed in the used fuel management area
ndash Provides a forum to prioritize and coordinate RampD globally
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
79copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
copy 2016 Electric Power Research Institute Inc All rights reserved
Chuck OlexicTechnical Advisor
Used Fuel and High Level Waste Action Plan Committee Meeting
Wednesday August 31 2016
2016 Nuclear Sector Member Satisfaction
Date 05 August 2016 Rev 0
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
81copy 2016 Electric Power Research Institute Inc All rights reserved
Member Satisfaction - Background EPRI has captured member satisfaction
feedback in various forms for many years
Current member satisfaction survey adopted by Board in 2006
Results reviewed regularly with Boardndash one of Corporate Performance Indices (CPIs)
Member feedback used to drive continuous improvement across EPRI
Helps prioritize efforts ndash focus on areas with greatest impact on
satisfaction
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
82copy 2016 Electric Power Research Institute Inc All rights reserved
Nuclear Member Satisfaction Survey Results
Overall Performance
Ease of Doing Business
Technical Program Value
Overall Satisfaction
2015 Results
2010-2015 Trend
923
Overall Performance
Ease of Doing Business
Technical Program Value
861
932
924
75
80
85
90
95
100
2010 2011 2012 2013 2014 2015
bull Impact of research on improving my business
bull The programs strategic priorities and directions
bull Quality of research results
bull Relevance of research carried out by the program
bull Technical staff expertise
Top ranked aspects of EPRI Experience
Who completed the Survey
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
83copy 2016 Electric Power Research Institute Inc All rights reserved
Category Initiative Timeframe
Research and Development
bull Research Focus Areasbull Project Overview Formsbull Quality Management Program Implemented 2016
Tech Transfer
bull Executive Summarybull Onsite EPRI updatesregional meetingsbull International workshopsbull International NPCbull Digital Strategy (ongoing)
Implemented 2016
Simplificationbull On-line Pricingbull Invoice Reviewbull New Pricing Model
Implemented 2016
Website bull New Search Enginebull Member Center Improvements Implemented 2016
Improvement Initiatives
Listening and Responding to the Feedback of our Members
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
84copy 2016 Electric Power Research Institute Inc All rights reserved
Digital Delivery Enhancements
Becomes
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
85copy 2016 Electric Power Research Institute Inc All rights reserved
Becomes
Digital Delivery Enhancements
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
86copy 2016 Electric Power Research Institute Inc All rights reserved
New Search EngineThe search engine gets smarter over
time based on use
It tracks what people search and where they go with the results
The more the search engine is used the faster it learns
As it learns features such as relevance and search term recognition will
dramatically improve and as a result improve your search experience
You make the search engine better by using it
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
87copy 2016 Electric Power Research Institute Inc All rights reserved
SectorProgram Specific Improvement Initiatives
Formal solicitation of new project ideas from MembersProgram prioritization using Research Focus Areas
ndash Webcast to review Research Focus Area selectionndash Webcast to review projects during prioritizationndash Earlier start to prioritization to provide ample time for feedback
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
88copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components hellip1 Who you are
without a name and organization we canrsquot count your input
2 Number of years you have been an Advisor
3 How wersquore doing
4 How you assess EPRI value
5 Key improvement in ease of doing business
6 Value you have received from this Program
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
89copy 2016 Electric Power Research Institute Inc All rights reserved
Survey instrument
Key components7 Rate each statement based on how
satisfied you are8 Rank the top 5 statements as
indicated in the instructions9 Would you recommend EPRI10If you are not satisfied with us in any
area please tell us why
9
10
7
8
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
90copy 2016 Electric Power Research Institute Inc All rights reserved
2015 Nuclear Member Satisfaction Scores By Area le86 87-90 ge91
Program Area Surveyed Cos Response Overall
PerformanceTechnical
Program ValueEase of Doing
BusinessOverall
Satisfaction Total
Nuclear Sector Council 1939 487 944 966 811 933 913
Materials Degradation Aging 1840 450 915 921 842 921 900
Fuel Reliability 1540 375 895 914 895 895 900
Used Fuel and High-Level Waste Management 1640 400 968 960 905 978 953
Nondestructive Evaluation 1340 325 900 927 818 900 886
Equipment Reliability 3040 750 910 912 838 907 892
Risk and Safety Management 1640 400 922 944 911 911 922
Strategic Initiatives (ANT and LTO) 2040 500 950 957 907 957 942
Chemistry Low-Level Waste and Radiation Management 1540 375 944 944 888 958 933
Total 923 932 861 924 910
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
91copy 2016 Electric Power Research Institute Inc All rights reserved
TogetherhellipShaping the Future of Electricity
