Westinghouse Non-Proprietary Class 3
LOCA Equivalent Clad Reacted (ECR) Criteria
NRC/Westinghouse MeetingRockville, MD
August 17, 2005
SHdel �Westinghouse
*BNFL Slide 1 OWestinghouse
LOCA Equivalent Clad Reacted (ECR) Criteria
ACRS subcommittee meeting on Reactor Fuels met on July 27, 2005
Ralph Meyer of NRC/RES presented a summary of the Argonne National Labs(ANL) program and their proposed LOCA criteria which was:
* ECR including both operational corrosion and transient oxidation <17%with the transient oxidation calculated by Cathcart-Pawel (C-P)
* Total time for transient < 2700 sec (45 minutes)* Peak Cladding temperature (PCT) < 2200 OF
This was unexpected since ANL had earlier issued an embrittlement correlationwhich was more phenomenological based
0 BNFL Slide 2 QWestinghouse
LOCA Equivalent Clad Reacted (ECR) Criteria
ANL presented the results of LOCA simulation testing performed at ANL
ANL program plan is to wrap-up the program following the completion of theirradiated ZIRLOTm and M5 tubing tests and the integral test of the HBR rodsegments
EPRI and ANATECH both made presentations which claimed that there are stillunanswered questions from the ANL testing and that the ANL results do notcorrelate with the results from other programs
*BNFL Slide 3 Westinghouse
(BNFL Slide 3 OWestinghouse
LOCA Equivalent Clad Reacted (ECR) CriteriaFANP presented joint EDF/CES/FANP data which showed much greaterreduction in post test ductility as a function of hydrogen compared to ANL data
Rationale for this appears to be the direct quench used in the French tests
Apparently this lock in the high temperature morphology in the P-layer, whereslower cooling provided time for segregations of oxygen and hydrogen in the II-layer providing greater ductility
NRC/RES stated that EPRI was not doing enough work to develop new limits, butonly enough to verify the existing interpretation of the LOCA limits for highburnup fuel
*BNFL Slide 4 OWestinghouse
LOCA Equivalent Clad Reacted (ECR) Criteria
ACRS question related to "What is the impact of up and down temperaturesvariations during high temperature oxidation on ECR and post test ductility?
Slide 5 ���We�tfnghouse
*BNFL Slide 5 O@Westinghouse
Westinghouse Non-Proprietary Class 3
Reactivity Initiated Accident (RIA) Criteria
NRC/Westinghouse MeetingRockville, MD
August 16, 2005
*BNFL Slide 6 9 Westinghouse(BNFL Slide 6 OWestinghouse
Reactivity Initiated Accident (RIA) Criteria
NRC/RES presented a summary of their analysis of RIA tests and his proposedcriteria. The most limiting aspect of the proposed criteria was the collapse of thecoolability limit onto a low cladding failure limit. The cladding failure limit wasgiven as a function of maximum fuel rod corrosion
EPRI and ANATECH presented the industry proposed criteria and the methodsused to produce it
Westinghouse presented summary of comments on proposed RIA criteria alongwith a sample analysis to demonstrate how limited the volume was of the coreclose to peak power and how unlikely conditions of high rod worth were
9 BNFL Slide7 OWestinghouse
Reactivity Initiated Accident (RIA) Criteria
ACRS indicated that they thought the N RC/RES proposed criteria was veryconservative
ACRS indicated that although they thought separate coolability and clad failurelimits were reasonable, they were skeptical that the onset of fuel melt was thebest limit and a lower one might be easier to justify
*BNFL Slide 8 �WestinghouseGBNFL Slide 8 OWestinghouse
Reactivity Initiated Accident (RIA) Criteria
ACRS was skeptical of the methods ANATECH used to treat cladding test data todevelop critical strain energy density (CSED) relationships as a function oftemperature and oxide thickness.
ACRS though the method non-conservative, and the overall method usingFALCON too obscure to easily understand
ACRS was skeptical that oxide spalling could be ruled out and thought that testswith spalled cladding should be included in developing the limit as was done byNRC/RES
*BNFL Slide9 Westinghouse
Westinghouse Non-Proprietary Class 3
AGENDAWestinghouse Semi-Annual Fuel Performance Update
August 16,2005Westinghouse Office
Rockville, MD
Tuesdav, Aue 16
8:00- 8:10 am
8:10 - 8:20 am
8:20- 10:15 am
10:15- 10:30am
10:30- 11:00am
11:00 - 11:20 am
11:20 - 11:40 am
11:40 - 11:50 am
11:50 - 1:00 pm
1:00 - 3:00 pm
3:00 - 3:15 pm
3:15 - 3:35 pm
3:35 - 4:00 pm
4:00 - 4:30 pm
4:30 - 4:50 pm
4:50 - 5:00 pm
BWR Fuel Update
Welcome
BWR Organization & Overview
Fuel Performance Update
Break
Application of European Experience Baseto U.S. Plants
] 1a"c Nuclear Benchmark Results
Westinghouse BWR Short & Long TermInteractions with the USNRC
Wrap-up
Lunch/Informal Discussion between NRC,Customers & Westinghouse
PWR Fuel Update
Fuel Performance Update
Break
Oden CHF Loop Update
[ ].C Creep/Growth Test
Reactivity Insertion Accident Feedback
Update on APA DevelopmentActivities
Wrap-up
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DRESS IS BUSINESS CASUAL
Westinghouse Non-Proprietary Class 3
Westinghouse Presentationon
Westinghouse Fuel Performance Update MeetingBWR / PWR Fuel Update
(Slide Presentation of August 16, 2005)
Westinghouse Electric Company LLCP.O. Box 355
Pittsburgh, PA 15230-0355
O 2005 Westinghouse Electric Company LLCAll Rights Reserved
Westinghouse Non-Proprietary Class 3
Westingho usevA BNFL Group company
*BNFL Slide 1 (OWestinghouse
Westinghouse Non-Proprietary Class 3
BWR Fuel Performance Update
NRC/Westinghouse MeetingRockville, MDAugust 2005
BNFL ��Westinghouse
@>BNFL Slide 2 (Westinghouse
Outline of PresentationOStatistics 0 Development
* Deliveries OSecondary FuelDegradation ProgrameBurnup
*Failures @Fuel PerformanceIn-Reactor Performance
*Pellet*Cladding
e Liner*Outer Component
*Channel
ProgramOSummary
*BNFL Slide 3 @ Westinghouse
BWR Fuel Deliveriesa, c
BNFL Westinghouse
(DBNFL Slide 4 GWestinghouse
BWR Fuel Burnup Experience, 2004a, c
*BNFL Slide 5 OWestinghouse
All Fuel Failures in Westinghouse 1 OxI 0 fuela, c
J*BNFL Slide 6 eWestinghouse
Primary Fuel FailuresWestinghouse BWR Experience
a, c
*BNFL Slide 7 Westinghouse
Age Distribution of Debris Fretting Failuresa, c
*BNFL Westinghouse
(DBNFL Slide 8 -Westinghouse
Axial Distribution of Debris Fretting Failuresa,c
BNFL Westinghouse
(BNFL Slide 9 Wefstinghouse
Outline of PresentationOStatistics 0 Development
*Deliveries*Burnup*Failures
@In-Reactor Performance*Pellet*Cladding
* LinerI *eOuter Component
*Channel
OSecondary FuelDegradation Program
@Fuel PerformanceProgram
OSummary
BNFL ��Westinghouse
(BNFL Slide 1 0 MWestinghouse
What is ADOPT?a, c
'I
(DBNFL Slide 1 1 -kWestinghouse
Technical Objectivesa, c
9 BNFL Westinghouse
(DBNFL Slide 12 (Westinghouse
Development of ADOPTa, c
*BNFL Slide 13 O)Westinghouse
ADOPTDeliveries
a, c
j.
BNFL Westinghouse
(qBNFL Slide 14 MWestinghouse
ADOPT - Next Stepsa, c
*BNFL Slide 15 WWestinghouse
Outline of PresentationOStatistics § Development
*Deliveries OSecondary FuelDegradation Program*Burnup
*Failures OFuel Performance@In-Reactor Performance
*Pellet*Cladding
*Liner*Outer Component
*Channel
ProgramOSummary
*BNFL Slide 16 ( Westinghouse
Liner Cladding - Backgrounda, c
-
t
*BNFL Slide 17 Westinghouse
Three Ramp Tests Performed in 2004-2005-
a, c
*BNFL Slide 18 O)Westinghouse
PIE after Stair-Case Ramp of 62 MWd/kgUSegment
a, c
*BNFL Westinghouse
' BNFL Slide 19 OWestinghouse
PIE after Stair-Case Ramp of 62Segment
MWd/kgU
a, c
(BNFL Slide 20 MWestinghouse
Secondary degradationMono and Liner Fuel byDegradation Type
a, c
*BNFL Slide 21 WWestinghouse
Liner Cladding - Summarya, c
*BNFL Slide 22 MWestinghouse
Outline of PresentationOStatistics 0 Development
* Deliveries OSecondary FuelDegradation Program*Burnup
*Failures @Fuel Performance0 In-Reactor Performance Program
*Pellet OSummary*Cladding
e Liner*Outer Component
*Channel
BNFL Westinghouse
(qBNFL Slide 23 '-'Westinghouse
Westinghouse BWR Claddinga, c
i
I
*BNFL Westinghouse
(DBNFL Slide 24 --Westinghouse
Cladding Outer Componenta,b,c
* Improve high burnupperformance
>Development of LK3
* Verify high burnup performance>Pool-side and hot-cell examinations of leading fuel rods
-Corrosion-Rod growth-Hydriding
(DBNFL.1;
BNFL Westinghouse
Slide 25 G@Westinghouse
LK3 - Achieved Burnupa, c
BNFL ISlide 26 i Westinghouse
Two-Life RodsRod positions I
ac
*BNFL Westinghouse
' BNFL Slide 27 MWestinghouse
Two-Life RodsPower history
F a,bc
L*)BNFL Slide 28 O)Westinghouse
Cladding CorrosionM'idspan Oxide Thickness by Cladding Type
a, b, c
LBNFL O WestinghouseSlide 29
Rod GrowthBy Cladding Type
a, b, c
OBNFL Slide 30 e)Westinghouse
Two-Life RodsPlanned hot-cell PIE
-
* Slide 31 OWestinghouse
Clad Hydrogen Pick-Upa, c
@BNFL Westinghouse
(OBNFL Slide 32 ftWestinghouse
5-6 Cycle LK3 and 6 Cycle LK2 & LK2+Secondary Phase Particle Size Distribution
r 'ma,C
L*BF Slide 33 O)Westinghouse
'I
Cladding Outer Component - Summarya, c
.,.
IBNFL
Westinghouse(DBNFL Slide 34 M)Westinghouse
Outline of PresentationOStatistics 0 Development
* Deliveries*BurnupeFailures
@ln-Reactor Performance*Pellet*Cladding
* Liner*Outer Component
*Channel
OSecondary FuelDegradation Program
OFuel PerformanceProgram
OSummary
(DBNFL Slide 35 (Westinghouse
B:WR Fuel PerformanceChannel Material Evolution
a, c
*DBNFL Slide 36 O)Westinghouse
Channel Corrosiona, b, c
(3BNFLl
Slide 37 *Westinghouse
Hydrogen Pick-Upa, b, c
.i
tI
(DBNFL Slide 38 -)Westinghouse
Hydrogen Pick-UpOuter Zry-2 Channel at 45 MWd/kg UF a, b, c
L*)BNFL Slide 39 W estinghouse
Channel Bow & Irradiation Induced Growtha, c
*BNFL Slide 40 (OWestinghouse
Channel Growtha, b, c
(DBNFL Slide 41 (Westinghouse
Channel Bow in Symmetric Latticea, b, c
BNFL Westinghouse
(DBNFL Slide 42 (IM-Westinghouse
Channel- Summarya, c
BNFL ��Westinghause
G)BNFL Slide 43 OWestinghouse
Outline of PresentationOStatistics 0 Development
*Deliveries*Burnup*Failures
OSecondary FuelDegradation Program
@Fuel PerformanceS I n-Reactor Performance Program
oPellet OSu mmary*Cladding
*Liner*Outer Component
I *Channel
* BNFL Westinghouse
(DBNFL Slide 44 M)Westinghouse
Alternative Cladding Alloys-Modified Zircaloy-2
a, c
*BNFL Slide 45 (O Westinghouse
Alternative Cladding AlloysZI RLOTM
a, c
.1
BNFL Westinghouse
(DBNFL Slide 46 O)Westinghouse
Alternative Cladding AlloysZI RLOTMF
-
a, c
L*BNFL Slide 47 (a Westinghouse
ZIRLOTM Channelsa, c
(DBNFL Slide 48 9Westinghouse
Outline of PresentationOStatistics 0 Development
* Deliveries OSeconda ry FueleBurnup Degradation ProgramoFailures @Fuel Performance
@In-Reactor Performance*Pellet*Cladding
ProgramOSummary
e LinereOuter Component
*ChannelI'
* BNFL (� Westinghouse
(BNFL Slide 49 GWestinghouse
Background & Time Schedulea, c
BNFL Westinghouse
(DBNFL Slide 50 -- estinghouse
Outline of PresentationOStatistics 0 Development
* Deliveries*Burnup*Failures
n-Reactor Performance
OSecondary FuelDegradation Program
OFuel PerformanceProgram01
oPellet OSum mary*Cladding
e Liner*Outer Component
eChannel
*BNFL Slide 51 @)Westinghouse
Fuel Performance ProgramAims and Goals
a, c
*BNFL Westinghouse
'mBNFL Slide 52 --Westinghouse
Fuel Performance ProgramSupport to other research amrocrams
. -w-
a, c
*BNFL Westinghouse
(DBNFL Slide 53 O)Westinghouse
Fuel Performance ProgramSummary of Rods Used for PIE
a, b, c
*DBNFL Slide 54 O)Westinghouse
F'uel Performance Program Continuation;I
a, c
.i
!
*BNFL Westinghouse
(DBNFL Slide 55 -Westinghouse
Outline of PresentationOStatistics 0 Development
e*Deliveries*Burnup
I *Failures§In-Reactor Performance
*Pellet*Cladding
OSecondary FuelDegradation Program
OFuel PerformanceProgram
OSummary
* LinereOuter Component
*Channel.,
*BNFL Westinghouse
(33BNFL Slide 56 O)Westinghouse
I
Summarya, c
(BNFL Slide 57 ftWestinghouse
Summary, cont.
.,
a,c
*BNFL Westinghouse
(DBNFL Slide 58 MWestinghouse
Westinghouse Non-Proprietary Class 3
Application of European Experience Base toU.S. Plants
NRC/Westinghouse MeetingRockville, MD
August 16, 2005
*BNFL Slide 1 �WesUnghause
(BNFL Slide I O)Westinghouse
Topics - Application of European Experience
* Background* Overall Approach* Application Confirmation
- Thermal-Hydraulic- Nuclear- Mechanical- Dynamic
- AQOs, CRDA, Sta bi I ity, LOCA
G BNFL Slide 2 Westinghouse
Background
* Recent 10 Year Reload Experience a, c
* Illustrates need for robust, flexible, and portablemethods
(DBNFL Slide 3 9SWestinghouse
Overall Approach - Processes
* Flexible and Robust methods versus validation of tunedmodels to each application
* Phenomenological methods applicable to intendedapplications
* Generalized methodology applicable to intended applications
* Formulation in terms of analyses input which capturing plant-specific requirements
* Application of performance data in an applicable manner
* Application of methods based on test data within data rangeor conservative
O BNFL Slide4 Westinghouse
I
Overall Approach - Fuel/Plant Data
* Major data transfer to support application ofgeneric methods to a specific plant - Steady-state
* Mechanical - core and legacy fuel data
i
* T/H - core, legacy fuel hydraulic andCPR data, core heat balance
* Nuclear legacy fuel description,previous cycle core follow, LPRMsystem, etc.
*BNFL Slide 5 (d)Westinghouse
Overall Approach - Fuel/Plant Data
Major data transfer to support dynamic applications
Plant geometries and volumes, water levels andtrips/alarms,Safety/relief/isolation/bypass/control valve data(e.g. pressures, timing, tolerances),recirculation/jet pump data, scram and RPSdata, LPRM/APRM/RBM/OPRM data,
containment, suppression pool, drywell data,
safety systems (LPCS, HPCS, HPCI, LPCI,ADS, etc) description and logic, seismic data
(DBNFL Slide 6 Westinghouse
Application Confirmation
* Steady-state Thermal-hydraulic modeling
* Confirmation that core pressure drops and flowsplits obtained from utility accurately predictedin Westinghouse T/H models
* T/H Compatibility evaluation for mixedWestinghouse fuel/Legacy fuel cores
* T/H models embedded in 3D core simulator(POLCA7)
9 BNFL Slide 7 Westinghouse
G)BNFL Slide 7 O@Westinghouse
Application Confirmation
* Nuclear Model Verification
* Analyses of cycles prior to initial loading ofWestinghouse fuel to confirm:
* Acceptable hot reactivity performance (keff)
* Acceptable cold reactivity predictions
* Acceptable power distribution predictions(comparison with TIP data)
9 BNFL Slide 8 Westinghouse
GBNFL Slide 8 (OWestinghouse
Application Confirmation
* Assembly/Rod performance verification
* Application of assembly and fuel rod corrosion,growth, etc.
a, c
*BNFL Slide 9 deWestinghouse
Application Verificationa, b, c
Slide 10 Westinghouse
*BNFL Slide 1I0 (DWestinghouse
Application Verificationa, b, c
*BNFL Slide 1 1 dWestinghouse
Application Verificationa, b, c
*BNFL Slide 1 2 l1Westinghouse
Application Verificationa, D, c
Slide 13 ���We�tinghause
*BNFL Slide 1 3 Wesincrhouse
Application Confirmation
* Fast AOO Models (BISON)a,c
Slide 14 Westinghouse
*BNFL Slide 1 4 (Westincghouse
Application Confirmationa, b, c
*BNFL 5!�de 15 Westinghouse
G)BNFL Slide 1 5 (O Westinghouse
Application Confirmationa, b, c
*BNFL Slide 16 Westinghouse
G)BNFL Slide 1 6 (i -) Westingrhouse
Application Confirmation
* CRDA Models (RAMONA) a, c
9 BNFL Slide 17 Westinghouse
(DBNFL Slide 1 7 O)Westinghouse
Application Confirmation
* Stability Models (RAMONA) a, c
*BNFL Slide 18 Westingha use
C)BNFL Slide 1 8 O)Westinghouse
Application Confirmationa,b,c
*BNFL Slide 19 ���Westinghause
1G3BNFL Slide 1 9 I@)Westinghouse
Application Confirmation
* LOCA Models (GOBLIN/DRAGON/CHACHA) a, c
Slide 20 ���Wesflnghouse
*BNFL Slide 20 (OWestinghouse
Westinghouse Non-Proprietary Class 3
I ]ac Nuclear Design Benchmark
NRC/Westinghouse MeetingRockville, MD
August 16, 2005
Slide 1 ��Westinghouse
*)BNFL Slide 1 _)Westinghouse
Introduction
Overview:BWR Nuclear Design Code System
Nuclear Benchmark:[ ac Cores
Summary and Conclusions
*)BNFL Slide 2 d2Westinghouse
Overview
* Neutronic Codes for BWR steady State Nuclear Design
+ PHOENIX4: 2D multi-group transport theory codeused to calculate lattice physics constants
+ POLCA7: 2-group nodal code used for 3-dimensionalsimulation of nuclear and thermal-hydraulicconditions in BWR cores
*BNFL Slide 3 Westinghouse
GBNFL Slide 3 eWestinghouse
Overview
Figure 1.1: Westinghouse Code System for BWR Nuclear Design and Analysis
FOBUS: Monte Carlo transporttheory code for burnableabsorber cross sectiongeneration
HEBE & Library processing codesPHULCAN: for nuclear cross section
data and depletion chains
IFIGEN: Input data generation forPHOENIX
PHOENIX: Two-dimensional multi-group transport theory codefor lattice physics constants
CoreLink & PHOENIX outputTABBE: processing codes for
nuclear data generation
POLCA: Three-dimensional, two-group nodal code forsteady-state reactor coresimulation
(DBNFL Slide 4 9dWestinghouse
Overview
* Approved Topical Reports for PHOENIX/POLCA:
+ BR 91-402: ABB Atom Nuclear Design and AnalysisPrograms for Boiling Water Reactors: ProgramsDescription and Qualification, May 1 991
+ CENPD-390-P-A: The Advanced PHOENIX andPOLCA7 Codes for Nuclear Design of Boiling WaterReactors, December 2000.
* Slide 5 Si5Westinghouse
Overviewa, c
*BNFL Slide 6 dWestinghouse
Overview,a, c
*BNFL ld7WestinghouseSlide 7
Overviewa, c
(DBNFL 9WestinghouseSlide 8
Overview
* The hot target keff determined from the core follow is usedfor the design cycle to predict+ Cycle length+ Number of fresh assemblies+Enrichment level+Hot excess reactivity+ Control rod patterns
BNFL Slide 9
Westinghouse@)BNFL Slide 9 IWesinghouse
Overview
* The cold target keff determined from the past cyclesmeasurement is used for the design cycle to predict
+Cold shutdown margin+Burnable absorber design+Standby Liquid Control System+Startup prediction
(SLCS) Verification
*BNFL Slide 1 0 dWestinghouse
Overview
* TIP and other nuclear benchmark comparisons are used to verifyhow well the axial and radial power distributions are computed
+Used as a guide in establishing the design thermal margins
... POLCA meas
100
90 ______ _
8070
60
50
40
30
20
10
00 20 40 60 80 100 120 140
OBNFL Slide 1 1 (BlWestinghouse
Overview
* In Summary, the Nuclear Benchmark
+gives confidence that BWR core is correctly modeled
+forms the basis for cycle nuclear design
+provides starting point for licensing analyses
*BNFL Slide 1 2 SWestinghouse
OverviewPHOENIX4/POLCA7 Codes Application
PHOENIX4/POLCA7 have been used in:
Plant Name Reactor Class Size (Bundle)
[ ]a,c BWR-6 624
[ ]a,c BWR-6 648
[ ]a,c BWR-4 764
[ ]a,c BWR-3 724
KWU Designs
Westinghouse-Atom
Designs1 _________________________________ .1. i a
OBNFL Slide 13 d1Westinghouse
Benchmark Results
I ]ac Nuclear Benchmark
* Hot keff results from core follow
* Cold critical measurements keff results
* TIP comparison+Nodal RMS+Radial RMS
resu Its
Slide 14 Westinghouse
OBNFL Slide 1 4 OWestinghouse
Benchmark Results: General Informationa, c
Slide 15 Westinghouse
*BNFL Slide 1 5 (OWestinghouse
Benchmark Results: Core Reactivitya, c
Slide 16 Westinghouse
*BNFL Slide 1 6 (aWestinghouse
Benchmark Results: Core Reactivitya, c
*BNFL Slide 1 7 (S7Westinghouse
Benchmark Results: Core Reactivity,a, c
*BNFL Slide 18 ��Westinghouse
G)BNFL Slide 1 8 O@Wesincghouse
Benchmark Results: Core Reactivitya, c
l
BNFL Slide 19 �Westinghauseg"5BNFL Slide 1 9 )Westincghouse
Benchmark Results: Core Reactivitya, c
9 BNFL Slide 20 Westinghouse
OBNFL Slide 20 (a Westinahouse
Benchmark Results: Core Reactivitya, c
G)BNFL Slide 21 9lWestinghouse
Benchmark Results: Core Reactivity,a, c
l
9 BNFL Slide 22 Westinghouse
(DBNFL Slide 22 O@Westinghouse
Benchmark Results: Cold Critical,a, c
l
*BNFL Slide 23 (S2Westinghouse
Benchmark Results: Cold Criticala, c
Slide 24 Westinghouse
*BNFL Slide 24 G@Wesfing~house
Benchmark Results: Cold Criticala, c
9 BNFL Slide 25 O@Westinghouse
)
Benchmark Results: TIP Comparisona, c
*BNFL Slide 26 Westinghouse
I
Benchmark Results: TIP Comparisona, c
(DBNFL Slide 27 (OQWestinghouse
I
Benchmark Results: TIP Comparison, a, c
Slide 28 Westinghouse
OBNFL Slide 28 (OWestinahouse
Benchmark Results: TIP Comparison,a, c
*BNFL Slide 29 (a Westinghouse
20
Summary and Conclusions
* Hot keff Core Follow Results+ Post Uprate Cycles consistent and stable, good confidence on
hot target keff curves to be selected for designs
* Cold Critical Results+Few results, but considerably consistent
* TIP Comparison Results+ Larger differences are as expected in the first few cycles of
simulation
+Large variability on RMS differences is consistent with neutronTIP experience
BNFL Slide 30 Westinghouse
Westinghouse Non-Proprietary Class 3
USNRC - Westinghouse BWR Short and LongTerm Interactions with the USNRC
NRC/Westinghouse MeetingRockville, MD
August 16, 2005
*BNFL Slide 1 Westinghouse
(DBNFL Slide I OWestinghouse
Topics - USNRC/Westinghouse StrategicalDiscussion* Planned Submittals* Application Implementations* Exelon Related Issues* Open
*BNFL Slide 2 Westinghouse
(DBNFL Slide 2 S)Westinghouse
Planned Submittals'p, c
*BNFL Slide 3 (eWestinghouse
Planned Submittalsa. c
DBNFL Slide 4 SlWestinghouse
Application Implementationsa, c
Slide 5 Westinghouse
BNFL Slide 5 O)Weslinghouse
Exelon Related Issuesa, c
Safety Limit Submittal-Format or guideline requirements from the USNRC?
*BNFL Slide 6 SeWestinghouse
Open
* Any advisement from USNRC on Sump Screen LOCAissue specific for BWR application-Westinghouse is keenly aware of PWR concerns and some
impending BWR concerns, what would the USNRC like forWestinghouse to be doing-soon or to be prepared for concerningBWR?
* Other?
*BNFL Slide 7 (SWestinghouse
Westinghouse Non-Proprietary Class 3
PWR Fuel Performance Update
NRC/Westinghouse MeetingRockville, MD
August 1 6, 2005
9 BNFL Slide 1
Westinghouse(DBNFL Slide 1 OWestinghouse
Outline* Fuel Reliability Overview A��
* 17 OFA Root Cause Investigation Update and recent PIE results
* Future PIE & Hot Cell Plans
* Status of LTA Programs
* RCCA Update
*BNFL Slide 2 Westinghouse
(DBNFL Slide 2 GWestinghouse
Westinghouse PWR Fuel Reliabilitya, c
()BNFL Slide 3 Bd)Westinghouse
Leakage Mechanisms in Westinghouse PWR Fuel: 2004a, c
Slide 4 ���Westinghause
*BNFL Slide 4 O@Westinghouse
Leakage Mechanisms in Westinghouse PWR Fuel:2005 YTD (May)
a, c
Slide 5 ��Qwestinghause
*BNFL Slide 5 O@Westinghouse
Fuel Performance Trenda, c
Slide 6 Westinghouse
*BNFL Slide 6 (OWestinlghouse
2004 - 2005 Leaking Rods by Major Product Familya,c
*BNFL Slide 7 Westinghouse
G)BNFL Slide 7 O)Westinghouse
Grid-Rod Fretting Solutions Being Implementeda, c
*BNFL Slide 8 ���WestinghauseC)BNFL Slide 8 OWesinghouse
1 7x1 7 RFA/RFA-2 Experiencea, c
Slide 9 Westinghause
*BNFL Slide 9 OWestinghouse
Current Status of RFAa, c
Siide 10 ���Wesfinghause
*BNFL Slide 1 0 (I)fWestinghouse
CE Improved Designs Implementationa, c
*BNFL Slide 11 c�Westinghause
(DBNFL Slide I I OWestinghouse
Summarya.C-1 -
Slide 12 Westingha use
*BNFL Slide 1 2 (OWestinghouse
Outline* Fuel Reliability Overview
* 17 OFA Root Cause Investigation Update and recent PIE results
* Future PIE & Hot Cell Plans
* Status of LTA Programs
* RCCA Update
Id|
9 BNFL Slide 13 Westinghouse
(DBNFL Slide 1 3 (Westinghouse
17 OFA Fuel Performance -l,
*BNFL Slide 14 Westinghouse
G)BNFL Slide 1 4 (a Westinghouse
Recent 1 7 OFA PIE Results - [ I a,ca, c
OBNFL*BNFL Slide 15 Westinghouse
Slide 1 5 OWestinghouse
Recent 17 OFA PIE Results - [ Ia,c
a, c
9 BNFL Slide 16 Westinghouse
(BNFL Slide 1 6 (Westinghouse
1 7x1 7 OFA Leaking Fuel Since 2002a, c
9 BNFL Slide 17 Westinghouse
C)BNFL Slide 1 7 O)Weslinghouse
Proactive Approach to Identify Leakage Mechanisms in 17 OFA Fuela, c
Siide 18 ��Westinghouso
*BNFL Slide 1 8 (O Westinghouse
Potential Leakage Mechanisms a, cT
BNFL Slide 19 Westinghouse
-OBNFL Slide 1 9 (IM)Westinghouse
Summary of Actions to Address Most Likely OFA Leakage Mechanismsa, c
Slide 20 ��Westinghause
*BNFL Slide 20 OWestinahouse
Revised pellet chip criteria statusa, c
G)BNFL Slide 21 9dWeslinghouse
Outline* Fuel Reliability Overview
* 17 OFA Root Cause Investigation Update and recent PIE results
* Future PIE & Hot Cell Plans
* Status of LTA Programs
* RCCA Update
9 BNFL Slide 22 Westinghouse
(DBNFL Slide 22 (O)Westinghouse
Planned Inspections for 1 7x1 7 OFAa, c
*BNFL Slide 23 ���Westinghause
(DBNFL Slide 23 (Westinghouse
Leaking Rod Hot Cell Programa, c
Slide 24 Westinghouse
*BNFL Slide 24 (@Westincrhouse
Outline* Fuel Reliability Overview
* 17 OFA Root Cause Investigation Update and recent PIE results
* Future PIE & Hot Cell Plans
* Status of LTA Programs
* RCCA Update
46��
*BNFL Slide 25 SWestinghouse
Westinghouse High Burnup ZIRLOT LTA Summarya, c
*BNFL Slide 26 Westinghouse
G)BNFL Slide 26 OWestinghouse
Other Test Programsa, c
S!ide 27 Westinghouse
*BNFL Slide 27 OWestinghouse
Status of Optimized ZIRLOM LTA Programsa, c
BNFL Slide 28 Westinghouse
(DBNFL Slide 28 (OWestinghouse
Outline* Fuel Reliability Overview
* 17 OFA Root Cause Investigation Update and recent PIE results
* Future PIE & Hot Cell Plans
* Status of LTA Programs
* RCCA Update
*BNFL Slide 29 l2Westinghouse
I Ia,c Separated RCCA Rodlet* One of twenty-four rodlets separated from a single EP-RCCA
- rodlet was located in the thimble tube of host fuel assembly- event occurred during Cycle 10 and was discovered at EOC-10- no affect on RCCA insertion during plant shutdown at EOC
* RCCA was manufactured prior to 1995
Slide 30 Westinghouse
*BNFL Slide 30 (GWestinghouse
Root Cause Status* Final Westinghouse CARB review performed in January, 2005
* Additional corrective actions completed 2005 YTD
- [ I a, c
- [- [
I a,c
I a, c
* Longer-term corrective actions
* Evaluate current RCCA design
*BNFL Slide 31 (S 3Westinghouse
l
[I a,c - Possible Separated RCCA Rodlet(s)
* No further RCCA performance issues
* Poolside PIE scheduled forthe next outage in FaIl 2005
Slide 32 Westinghouse
*BNFL Slide 32 (OWestinghouse
4
[ Iac Incomplete Rod Insertion* [ a1C has a non-standard core comprising non-Westinghouse 1 4x1 4 fuel
design with an 8 ft active length
* The RCCAs are the Westinghouse EP design and are close to their design lifeof 12 EPFY
* A single RCCA stuck in the fuel assembly dashpot
* Swelling of the absorber was the most probable cause
* Westinghouse is working to ensure this experience is integrated into its RCCAoperating guidelines
(DBNFL Slide 33 (BiWestinghouse
I
Summary* Fuel performance has improved in some areas, but deteriorated in others
* Programs and action plans are in place and being implemented
* Fuel designs susceptible to grid to rod fretting being replaced with improvedproducts that are performing well
* Most pressing issue at this time is resolution of 1 7X1 7 OFA leakers
- [- [
I a, c
] a, c
9 BNFL Slide 34 Westinghouse
(DBNFL Slide 34 (Westinghouse
Westinghouse Non-Proprietary Class 3
Oden CHF Loop Update
NRC/Westinghouse MeetingRockville, MDAugust 2005
(DBNFL Slide I BdWestinghouse
Outline* Overview of Oden Facility
* Status of Loop Design/Construction
* Test Loop Description and Characteristics
* Qualification Test Plan
* Schedule
Slide 2 Westinghouse
*BNFL Slide 2 (SWestinghouse
Vasteras Fuel T/H-Testing Facilitya,c
*BNFL Slide 3 Sd3Westinghouse
Loop Design & Construction (1) - schematica, c
*BNFL Slide 4 SWestinghouse
Loop Design & Construction (2)a, c
(BNFL Slide 5 BeWestinghouse
Loop Design & Construction (3)a, c
(DBNFL Slide 6 BeWestinghouse
Loop Description, Characteristicsa, C
*BNFL Slide 7 Westinghouse
(DBNFL Slide 7 OWestinghouse
Qualification Test Plan (1) - Objectives1. Characterize Oden loop response to changing conditions
2. Demonstrate Oden repeatability
3. Benchmark Oden data to HTRF data
4. Develop experience base
*BNFL Slide 8 Westinghouse
(BNFL Slide 8 SWestinghouse
Qual ification Test Plan (2) - Overviewa, c
*BNFL Slide 9 Westinghouse
(DBNFL Slide 9 G)Westinghouse
Qualification Test Plan (3) - Current Test Geometry Selection
a, c
-
BNFL Slide 10 Westinghouse
(DBNFL Slide 10 SWestinghouse
v
Schedulea,c
Slide 11 Westinghouse
* Slide I 1 O)Weslinghouse
Westinghouse Non-Proprietary Class 3
]a~c Creep/Growth Test
Westinghouse/NRC MeetingRockville, MD
August 16, 2005
*BNFL Slide I dWestinghouse
Presentation Outline
* Test overview and status
* Optimized ZIRLO' irradiation growth and creep
* Determined sample stresses
* Tensile and compressive stress irradiation creep
* Completion of NRC commitments
9 BNFL Slide 2 Westinghouse
(DBNFL Slide 2 (SWestinghouse
Test Status* Test assembly Al
- Completed irradiation (1 cycle)- Completed PIE/NDE measurements- Evaluation of NDE data is in-progress
* Optimized ZIRLO I AD/D 0 data are available* ZIRLOt m AD/Do tensile and compressive stress data are available
- Destructive examination may be performed after the NDE evaluation iscomplete
* Irradiation is continuing for test assemblies A2, A3, A4 & A5
(DBNFL Slide 3 Westinghouse
Irradiation Schedule, a, c
Slide 4 ��QWesflnghouse
OBNFL Slide 4 (OWestinghouse
Data Acquisition Measurement Methodology 7 a, b, c
(DBNFL Slide 5 9SWestinghouse
Irradiation Growth and Irradiation Creep Data (1/2)* Irradiation growth measurements were made on tube samples open to coolant
water flow- Ensured a stress-free condition
* Irradiation creep measurements were made on internally Helium pressurizedtube samples- Irradiation creep, AD/D0(ic), was calculated from the total diameter
change, AD/D 0 (total), and the irradiation growth, AD/Df(ig), accordingto, AD/D0(ic) = AD/D 0 (total) -AD/D0(ig)
(DBNFL Slide 6 *i6Westinghouse
Irradiation Growth and Irradiation Creep Data (2/2)
* OD accuracy is outstanding
- [ Ia, b, c laser OD measurements on each sample
- 95% confidence interval is [ Ia, b, c
- Pre and post-test measurements were performed with the same facility-minimizes measurement errors
* Each data point in the following graphs represents one sample
*BNFL Slide 7 (SeWestinghouse
ZIRLOTM and Optimized ZIRLOTM Irradiation Growtha, bc
*DBNFL Slide 8 (SeWeslinghouse
ZIRLOTM and Optimized ZIRLOT Irradiation Creepa, b, c
7
9 BNFL Slide 9 Westinghouse
@IBNFL Slide 9 (OWeslinghouse
ZIRLOTM and Optimized ZIRLOT Resultsa, b, c
0 BNFL Slide 10 Westinghouse
(DBNFL Slide 1 0 S)Westinghouse
Creep and Growth Sample Designa, bc
* Evaluated the sample temperatures, the internal Helium gas pressure andhoop stress using the actual gamma-heat rate- All test parameters are based on experimental measurements when the
dosimetry analysis is finalized (AD/DoT, ae & 4)t)
Slide 11 Westinghouse
*BNFL Slide 1 1 Owestinghouse
Creep and Growth Sample Designa, b, c
*BNFL Slide 1 2 SeWestinghouse
Determination of the Gamma-Heat Rate & Hoop Stress* Performed parametric calculations of the sample hoop stress as a function
of the gamma heat rate
I. I a, bc
* Actual gamma-heat rate is given by the maximum regression R2 coefficientassociated with AD/D 0(ic) versus hoop stress- Corresponds to the minimum deviation of the data from the regression
line- (Perfect regression fit is associated with an R2 coefficient of 1.0)
*BNFL Slide 13 Westinghouse
(DBNFL Slide 13 O@Westinghouse
Hoop Stress Variation with the Gamma-Heat Ratea, b, c
Slide 14 Westinghouse
*DBNFL Slide 14 (OWeslinghouse
Regression R2 Coefficient Versus Gamma-Heat Ratea, b, c
*BNFL Slide 1 5 Sd1Westinghouse
Irradiation Creep versus Hoop Stress, a,bc
9 BNFL Slide 16 ��Westinghouse
OBNFL Slide 1 6 (a)Westinghouse
Tension and Compression Irradiation Creep Results
* Gamma-heat rate is [ Ia, b,c
* Replicate sample-to-sample consistency is excellent
* Irradiation creep is the same in tension and compression for WestinghouseZIRLO™ and Optimized ZIRLO'- AD/D 0 (ic) versus se is [
- [-[ ]a, b c hoop stresses: [
I a, b,c
I a, b, c
]a, b, c compression and [ Ia, b, c tension
Siide 17 ��Westinghause
*BNFL Slide 1 7 (D)Westinchouse
Completion of NRC Commitments* Completed PAD 4.0 SER commitment in Section 2.1 to initiate a clad
irradiation growth and creep test to provide a more accurate measurement ofirradiation creep under tension and compression stresses and share the datawith the NRC
* Completed Optimized ZIRLO' SER commitment in Section 5.0, Item 7 a & b toreport the [ ]aC Creep/Growth Optimized ZIRLOt data and showOptimized ZIRLO' irradiation creep is consistent with ZIRLO'
* Confirmed that tension and compression irradiation creep of Westinghouse
ZIRLO' and Optimized ZIRLO' are equal- No impact on Westinghouse rod pressure analysis (Optimized ZIRLO' SER
Section 5.0, Item 7)
(BNFL Slide 18 Westinghouse
Conclusions
* Different processing methods such as PRXA or SRA may be used to fabricateOptimized ZIRLOTM with the same irradiation creep as ZIRLOT
lac data confirms creep behaviour for Ootimized ZIRLOT- r
* Irradiation creep is the same in tension and compression for Westinghouse
ZIRLOt and Optimized ZIRLO'- ]a c data confirms the Westinghouse model for tensile creep
* Westinghouse commitments to the NRC concerning the [Creep/Growth test are complete
Iac
J
Slide 19 Westinghouse
*BNFL Slide 1 9 O)Weslinghouse
Future Data Currently In-Process
]a, b, c
* Beneficial effect of hydrogen on reducing irradiation growth and creep isunder evaluation- Importantfordrystorage
Slide 20 Westinghouse
*DBNFL Slide 20 Oftetinghouse
Westinghouse Non-Proprietary Class 3
Reactivity Insertion Accident Feedback
NRC/Westinghouse MeetingRockville, MD
August 16, 2005I BNFL Slide 1 Westinghouse
gBNFL Slide I OWestinghouse
Status
* Tests in '90s indicated need to reexamine the limit for reactivity insertionaccidents (RIA)
* Using more accurate 3-D analyses provide significant margin compared toolder 1-D based analyses- So no safety concern in operating plants
* EPRI, representing the industry, submitted report recommending new limit
* Westinghouse submitted 3-D rod ejection methodology for review andreceived SER
* NRC-NRR rejected EPRI report and is proposing new limits
*BNFL Slide 2 S 2Westinghouse
Driver
* Would like to close out this issue- Creates uncertainty in licensing space- Is diverting resources- Permit licensing of high burnup fuel
* But with acceptable limits
(BNFL Slide 3 SeWestinghouse
NRC-NRR Proposed CriteriaSelect one of the following:
1. Ejected rod worth of $2.20 or less with oxide thickness of 70 microns, or$1.70 if greater oxide
2. Reactivity excursion should not exceed cladding failure threshold curve inRES RIL-0401 Figure 1
3. Dose calculations for rods exceeding limit, plus coolability limit based onlimiting pressure pulse resulting from fuel dispersal
)BNFL Slide 4 SeWestinghouse
-
RES RIL-0401 Figure 1300
A250
-O 200
>1X
100
50
<:~BWR cold RtA
0
0 10 20 30 40 50 60 70 80 90 100 110 120Oxide Thickness (u)
Figure 1. Cladding failure data with adjustments from the scaling analysis andlower-bound failure correlations. The lowest point at 80 microns of oxidethickness is for a test that has been discredited.
*BNFL Slide 5 Westinghouse(3BNFL Slide 5 O)Westinghouse
Ejected Rod Worth* Highly dependent on the control rod pattern, loading pattern and bank
insertion limits
* Based on most adverse allowable operational conditions
* Ejected rod worth has been increasing- Longer cycles (higher enrichments, axial burnup effects)- IRI concerns places feed fuel in most control rod locations
* Operation can impact ejected rod worth- Control rod shadowing- Cl PS
* Occurrence of operational restrictions even with $ 2.1 5
( BNFL Slide 6 Westinghouse
Feedback on ER Worth Limit* Would assume corrosion thickness is nominal value
* Rod ejection is a local event- Fuel enthalpy dependent on local peaking and core power- Significant local peaking only in area of ejected rod- Only neighborhood of ER sees significant fuel enthalpy increase- Fuel failure, if it occurred, would be local to ejected rod
* High oxide on high burnup rods- Low reactivity, lower peaking factor- Could restrict use of fuel from spent fuel pool
* Failure limit should reflect local fuel enthalpy
Q BNFL Slide 7 Westinghouse
Fuel Failure Limit
* Discussed in NRC/EPRI meeting on July 7, 2004 and ACRS FuelSubcommittee meeting on July 28, 2005- Difference in failure limits due to different methods of adjustment of
experimental data- Difference of opinion on need to include spalled cladding data
* Compromise position may include- Limit on fuel enthalpy increase of 100-125 cal/gm- Some reduction with burnup to reflect corrosion impact- Separate penalty for spalled cladding, if expected (25 cal/gm)
(BNFL Slide 8 OWetinghouse
Coolability Limit* Separate coolability limit is appropriate
* Limit can be set to prevent fuel melting- Pressure pulse would require much higher energy input- Dose calculation assumptions valid for whole transient
* Compromise position could include:- Initial limitofl75-200 cal/gm- Small reduction with burnup to reflect melting point change
*BNFL Slide 9 d)Westinghouse
Comparison of Potential LimitsI- - EPRI Coolability Limit -EPRI Failure Limit - RES RIL-0401 -W Interim Limit|
250 :
225
200E
M- 175
L 150,E
*; 125aL
s 100C
-6 75U-
50
25
0
.. ..--- - ............... .... ........... ... .. …*... ....
90 o0 OO 00000 0. 00000 OOo ee 000 ;OO OOO
io e 00 ooo8ooooooo
@0 ooooooooo 00oo oo0
o 0 0 G o 0 f a 0 o o o 0000o000 o
-------- _-------o
~~~~~~~~~~. .... .. ......... ......s___
REL RIL-0401 Values with Oxide ThicknessConverted to Bumup Using Best EstimateCorrosion Fit for ZirloTM
Coolability
Failure
-
-I.
10 20 300 40 50 60 70 80
Burnup (GWd/MtU)
(BNFL Slide 1 0 BWestinghouse
Realistic Conservatism* PWR rod ejection most limiting over very small and unlikely operational space
- EOC, HZP, rods at insertion limit and critical
* Conservatism applied to peaking factors and ejected rod worth
* The EPRI curves would be appropriate limits
* Some compromise position may be acceptable
G)BNFL Slide 1 1 SlWestinghouse
Summary
* Westinghouse believes NRC-NRR proposed limits should be revised
* Westinghouse will continue to work with EPRI to define industry position
* Westinghouse believes it is in the best interests of everyone to bring thisissue to closure
Slide 12 Westinghouse
*BNFL Slide 1 2 O)Westinghouse
Westinghouse Non-Proprietary Class 3
Update on APA Development Activities
NRC/Westinghouse MeetingRockville, MDAugust 2005
9 BNFL Slide 1 Westinghouse
GBNFL Slide I O)Westinghouse
NEXUS Project - Descriptionm1 ac
*BNFL Slide 2 dWestinghouse
ANC and Related Technology Developmenta,c
*BNFL Slide 3 deWestinghouse
ANC 9 / NEXUS Project - Status and Actionsa,c
*BNFL Slide 4 SdVWestinghouse
ANC 9 Production Rollout Project - Descriptiona, c
(*BNFL Slide 5 I@) Westinghouse
ANC 9 Production Rollout Project- Status and Actionsa, c
6-*BNFL Slide 6
Westinghouse(DBNFL Slide 6 (Westinghouse
ANC 9 / SPNOVA Merge Project - Status and Actionsa,c
* Slide 7 d7Westinghouse
WestinghouseA BNFL Group company
Slide 8 c��Westinghause
*IBNFL Slide 8 OWesinghouse
Westinghouse Non-Proprietary Class 3
AGENDAWestinghouse Semi-Annual Fuel Performance Update
August 17,2005Westinghouse Office
Rockville, MD
Wednesday, Au! 17 Licensing Review (Westinghouse & NRC)
8:00 - 9:00 am Brief Overview of Westinghouse OrganizationPWR/BWR Topicals and Schedule
I
[ ]a,c
]a,c[
I21c
9:00- 11:50 am General Licensing Concerns & Issues[
All
]a,c
11:50 - noon
noon - 1:00 pm
Wrap-upNext meeting
Lunch/Informal Discussion between NRC &Westinghouse
DRESS IS BUSINESS CASUAL
Westinghouse Non-Proprietary Class 3
Westinghouse Presentationon
Westinghouse Fuel Performance Update MeetingManagement Licensing Overview
(Slide Presentation of August 17, 2005)
Westinghouse Electric Company LLCP.O. Box 355
Pittsburgh, PA 15230-0355
°2005 Westinghouse Electric Company LLCAll Rights Reserved
I Westinghouse Non-Proprietary Class 3
estnghusA BNFL Group company
*BNFLL Slide I e)Westinghouse Nestinghouse
Westinghouse Organization(NRC Interface)
a, c
BNFL Slide 2 Westinghouse
GBNFL Slide 2 O)Westinghouse
Westinghouse Non-Proprietary Class 3
Topical Report Status
Westinghouse/NRC MeetingRockville, MD
August 16, 2005
*BNFL Slide 1 WestinghouseGBNFL Slide 1 (Westinghouse
PWR Topical Reports Under Reviewa, c
7
(DBNFL BNFL Slide 2 Westinghouse
Slide 2 -)Westinghouse
PWR Topical Reports Planneda, c
*BNFL Slide 3 eWestinghouse
BWR Topical Reports Under Review a,c___ ______________________________a
-
*BNFL Slide 4 Westinghouse
(DBNFL Slide 4 OWestinghouse
BWR Topical Reports PlannedaI C
Slide 5 Westinghouse
*BNFL Slide 5 (OWeslinghouse
BWR Topical Reports Planneda; ra, -9
*BNFL Slide 6 d6Westinghouse
I
Westinghouse Non-Proprietary Class 3
IRI Update
NRC/Westinghouse MeetingRockville, MD
August 17, 2005
@BNFL Slide 1 Westinghouse
(DBNFL Slide I Wefstinghouse
IRI Update - Background
* NRC Bulletin 96-01 and Draft Supplement regarding IRI for Westinghouse NSSS fleet
* WOG Program initiated to respond
a, c
* WOG Program Successful; NRC canceled plans to issue Supplement 1 to Bulletin 96-01
- Last WOG communication in January 2001 to NRC, and 2002 to WOG utilities
BNFL Slide 2 Westinghouse
(DBNFL Slide 2 -'Westinghouse
IRI Update -Burn-up Threshold Summary-
* IRI Burn-up Thresholda, c
BNFL Slide 3 Westinghouse
(DBNFL Slide 3 _)Weslinghouse
IRI Update - Recent Activities
* Overtures from several utilities to extend burnup threshold for fuel assemblies inrodded locations- Core Designs challenging threshold- No recent IRI issues- Preclude IRI, susceptibility evaluations- Extend BU threshold requiring IRI susceptibility evaluations
BNFL Slide 4 Westinghouse
()BNFL Slide 4 O)Westinghouse
IRI Update - Summary* Positive Aspects
* No IRI for instances with rodded assembly > burn-up threshold
* Improved fuel design features to resist IRI* Continued low risk of IRI at current approved limits
*9BNFL Slide 5 W estinghouse
Westinghouse Non-Proprietary Class 3
LOCA Equivalent Clad Reacted (ECR) Criteria
NRC/Westinghouse MeetingRockville, MD
August 17,2005
SIide� Westinghouse
*BNFL Slide 1 O)Westinghouse
LOCA Equivalent Clad Reacted (ECR) Criteria
ACRS subcommittee meeting on Reactor Fuels met on July 27, 2005
Ralph Meyer of NRC/RES presented a summary of the Argonne National Labs(ANL) program and their proposed LOCA criteria which was:
* ECR including both operational corrosion and transient oxidation < 17%with the transient oxidation calculated by Cathcart-Pawel (C-P)
* Total time for transient < 2700 sec (45 minutes)* Peak Cladding temperature (PCT) < 2200 OF
This was unexpected since ANL had earlier issued an embrittlement correlationwhich was more phenomenological based
( BNFL Slide 2 Westinghouse
LOCA Equivalent Clad Reacted (ECR) Criteria
ANL presented the results of LOCA simulation testing performed at ANL
ANL program plan is to wrap-up the program following the completion of the
irradiated ZIRLOTm and M5 tubing tests and the integral test of the HBR rod
segments
EPRI and ANATECH both made presentations which claimed that there are still
unanswered questions from the ANL testing and that the ANL results do not
correlate with the results from other programs
*BNFL Slide 3 leWestinghouse
LOCA Equivalent Clad Reacted (ECR) Criteria
FANP presented joint EDF/CES/FANP data which showed much greaterreduction in post test ductility as a function of hydrogen compared to ANL data
Rationale for this appears to be the direct quench used in the French tests
Apparently this lock in the high temperature morphology in the ,8-layer, whereslower cooling provided time for segregations of oxygen and hydrogen in the p-layer providing greater ductility
NRC/RES stated that EPRI was not doing enough work to develop new limits, butonly enough to verify the existing interpretation of the LOCA limits for highburnup fuel
GBNFL Slide 4 Westinghouse
LOCA Equivalent Clad Reacted (ECR) Criteria
ACRS question related to "What is the impact of up and down temperaturesvariations during high temperature oxidation on ECR and post test ductility?
9 BNFL Slide 5 Westinghouse
()BNFL Slide 5 S)Westinghouse
Westinghouse Non-Proprietary Class 3
Reactivity Initiated Accident (RIA) Criteria
NRC/Westinghouse MeetingRockville, MD
August 16, 2005
(*BNFL Slide 6 SWestinghouse
Reactivity Initiated Accident (RIA) Criteria
NRC/RES presented a summary of their analysis of RIA tests and his proposedcriteria. The most limiting aspect of the proposed criteria was the collapse of thecoolability limit onto a low cladding failure limit. The cladding failure limit wasgiven as a function of maximum fuel rod corrosion
EPRI and ANATECH presented the industry proposed criteria and the methodsused to produce it
Westinghouse presented summary of comments on proposed RIA criteria alongwith a sample analysis to demonstrate how limited the volume was of the coreclose to peak power and how unlikely conditions of high rod worth were
GBNFL Slide 7 Westinghouse
Reactivity Initiated Accident (RIA) Criteria
ACRS indicated that they thought the NRC/RES proposed criteria was veryconservative
ACRS indicated that although they thought separate coolability and clad failurelimits were reasonable, they were skeptical that the onset of fuel melt was thebest limit and a lower one might be easier to justify
Slide 8 Westinghouse
* Slide 8 O)Westinghouse
Reactivity Initiated Accident (RIA) Criteria
ACRS was skeptical of the methods ANATECH used to treat cladding test data todevelop critical strain energy density (CSED) relationships as a function oftemperature and oxide thickness.
ACRS though the method non-conservative, and the overall method usingFALCON too obscure to easily understand
ACRS was skeptical that oxide spalling could be ruled out and thought that testswith spalled cladding should be included in developing the limit as was done byNRC/RES
( BNFL Slide 9 Westinghouse