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babcock & wilcox nuclear energy

B&W mPowerTM ReactorIntegrated Systems Test Technical Report

06-00000392-001 (NP)Revision 001

November 2011

SmPower TM

1 a progressive energy solution

B&W mPowerTM Reactor ProgramBabcock & Wilcox Nuclear Energy, Inc.

109 Ramsey PlaceLynchburg, VA 24501

Babcock & Wilcox Nuclear Energy, Inc.a Babcock & Wilcox company

Document No. Title Rev. No.

06-00000392- B&W mPower TM Reactor 001001(NP) Integrated Systems Test Technical Report

SIGNATURES

Prepared By: Billy E. Bingham /9 .. 'V8 Cy'01

Technical Consultant Signature Date

Revievnd By: Eric Williams (X yI f 1/130/11

Manager of Safety Analysis Signature Date

Reviewed By: Chet Poslusny a t)L Awm. l ____

Licensing Slgnaturi' Date

Approved By: D. E. Lee j - |)/Zoe

IST Engineer Manager Signature Date

@2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

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06-00000392- B&W mPower TM Reactor001(NP) Integrated Systems Test Technical Report

RECORD OF REVISION

Revision Section(s) or Page(s) Description of Changes

0 N/A Initial Issue

Revision updates information about the IST1 All Sections design, test plan, analysis, and provides new

information about scaling of the IST.

02011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

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06-00000392- B&W rnPower Tm Reactor 001001(NP) Integrated Systems Test Technical Report

Table of Contents

1 . O V E R V IE W ......................................................................................................................................... 10

2 . S C A L IN G ............................................................................................................................................. 162.1 IST - B&W mPower Reactor Design Features at 425 MWt Power Level ............................... 162.2 IST - B&W m Power Com parison ............................................................................................ 182.3 Top - Down Scaling at 425 MW t ............................................................................................. 18

2.3.1 Single Phase Natural Convection ...................................................................................... 192.3.2 Scaling Anomalies ............................................................................................................. 202.3.3 Top down Scaling Conclusions ......................................................................................... 212.3.4 Assessment of Applicability of IST to Power Upgrade ...................................................... 22

2.4 Boftom -Up Scaling at 425 MW t ............................................................................................... 242.4.1 Safety Related Risk Perspective ....................................................................................... 252.4.2 Com ponents that Dom inate Each LOCA Phase ............................................................... 252.4.3 Recom m endations for B&W m Power Reactor Use of PIRT Results ................................ 272.4.4 Assessment of PIRT Recom mendation Relative to Power Upgrade ................................ 27

3. FUNCTIONS AND DESIG N REQUIREM ENTS .................................................................................. 383 .1 F u n c tio n s .................................................................................................................................. 3 8

3.1.1 Steam Generator Characteristics ...................................................................................... 383.1.2 Design Basis Event Testing .............................................................................................. 383.1.3 Operational Testing ........................................................................................................... 383.1.4 Flow Characteristics .......................................................................................................... 38

3.2 Reactor Coolant System Design Requirements ...................................................................... 393.2.1 ASM E Code Design Requirements ................................................................................... 393.2.2 IST Reactor Loop Design Requirements .......................................................................... 393.2.3 Instrumentation Requirements .......................................................................................... 403.2.4 Reactor Protection System and Engineered Safety Feature Activation Test

R e q u ire m e n ts .................................................................................................................... 4 33 .3 C o re S im u la tio n ....................................................................................................................... 4 4

4. SYSTEM DESCRIPTION .................................................................................................................... 454 .1 C o re S im u la to r ......................................................................................................................... 4 6

4.1.1 Core and Core Internals/Support ...................................................................................... 464.1.2 Core Sim ulator Heaters ..................................................................................................... 464.1.3 Reactor Vessel .................................................................................................................. 474.1.4 Power Supply .................................................................................................................... 48

4.2 Steam Generator ..................................................................................................................... 484 .2 .1 T u b e s ................................................................................................................................. 4 94 .2 .2 S h ro u d ............................................................................................................................... 4 94.2.3 Tube Support Plates .......................................................................................................... 49


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06-00000392- B&W mPower Tm Reactor 001001(NP) Integrated Systems Test Technical Report

4 .2 .4 T u b e s h e e ts ........................................................................................................................ 5 04.2.5 Steam Generator Instrumentation ..................................................................................... 504.2.6 Tube Rupture Sim ulation ................................................................................................... 51

4 .3 P re s s u riz e r ............................................................................................................................... 5 14 .3 .1 V e s s e l ................................................................................................................................ 5 14.3.2 Baffle Plate and Surge Arrangement ................................................................................ 514 .3 .3 S p ra y ................................................................................................................................. 5 14 .3 .4 H e a te rs .............................................................................................................................. 5 24.3.5 Instrumentation .................................................................................................................. 524.3.6 Code Safety Valves ........................................................................................................... 52

4.4 Reactor Coolant Pum p Region Sim ulator ................................................................................ 524.5 Other Reactor Coolant System Pipe Sections ......................................................................... 53

4 .5 .1 R is e r .................................................................................................................................. 5 34.5.2 Steam Generator/Pressurizer/Riser Junction .................................................................... 534.5.3 Pum p-Steam Generator to Reactor Vessel ....................................................................... 544.5.4 Reactor Coolant Support Loop .......................................................................................... 54

4 .6 L o o p In s u la tio n ......................................................................................................................... 5 4

5. ENGINEERED SAFETY FEATURE COMPONENTS AND DECAY HEAT REMOVAL ..................... 735.1 Emergency Core Cooling Trains .............................................................................................. 73

5.1.1 Emergency Condenser Cooling ........................................................................................ 735.1.2 Separator at Emergency Condensed Condensate Outlet ................................................. 745.1.3 Autom atic Depressurization Valves ................................................................................... 755.1.4 ECC Piping & Valves ......................................................................................................... 755.1.5 ECCS Insulation ................................................................................................................ 755.1.6 Ultimate Heat Sink ............................................................................................................. 755.1.7 UHS - Emergency Condenser Feedwater Pipe ................................................................ 765.1.8 UHS - Emergency Condenser Return Piping .................................................................... 765.1.9 ECCS Spargers ................................................................................................................. 765.1.10 Pipe Insulation and Support .............................................................................................. 76

5.2 Emergency Boron System ....................................................................................................... 775.3 Steam Generator Steam Vent ................................................................................................. 775.4 RW ST and Containment .......................................................................................................... 775.5 Steam and Feed Com ponent ................................................................................................... 785.6 Reactor Coolant Inventory and Purification Subsystem .......................................................... 78

6. COM PONENT COOLING W ATER SYSTEM ...................................................................................... 946.1 RCIPS Heat Exchangers Cooling ............................................................................................ 946.2 Loop Pum p Cooling ................................................................................................................. 946.3 Heater Rod Seal Cooling ......................................................................................................... 946.4 Feedwater Purification Heat Exchanger Cooling ..................................................................... 95


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06-00000392- B&W rnPower Tm Reactor 001001(NP) Integrated Systems Test Technical Report

7. STEAM , FEEDW ATER, AND CONDENSATE SYSTEMS ................................................................. 96

8. INSTRUMENTATION FOR CONTROL, PROTECTION, AND DATA ACQUISITION ........................ 98

9. CONTROL, PROTECTION, AND DATA ACQUISITION SYSTEMS .................................................. 999.1 Loop Inventory Control - RCIPS ............................................................................................. 99

9.1.1 Fixed Level Band Control .................................................................................................. 999.1.2 Level Band Floats with Power Level ................................................................................. 99

9.2 Loop Pressure Control ........................................................................................................... 1009.3 Loop Flow Control .................................................................................................................. 1009.4 Heater/Core Power Control .................................................................................................... 1009.5 Trace Heater Control ............................................................................................................. 1009.6 Reactor Protection and Engineered Safety Feature Activation System s .............................. 101

9.6.1 Reactor Protection System Setpoints for 425 MW t Equivalent Testing .......................... 1019.6.2 Engineered Safety Feature Activation System Setpoints ............................................... 1029.6.3 Additional Loop Protection .............................................................................................. 102

10. IST- B&W mPOWER REACTOR RELAP5 ANALYSES AT425 MWt ............................................ 10710.1 IST Modeling for RELAP5 ...................................................................................................... 107

10.1.1 Reactor Pressure Vessel ................................................................................................. 10810.1.2 Steam Generator ............................................................................................................. 1081 0 .1 .3 P re ss u riz e r ...................................................................................................................... 10 81 0 .1 .4 R is e r ................................................................................................................................ 1 0 910 .1 .5 D o w n c o m e r ..................................................................................................................... 10 910.1.6 Em ergency Core Cooling Systems ................................................................................. 10910.1.7 Heat Structures ................................................................................................................ 110

10.2 Confirmation of Scaling Factors at Steady State Conditions ................................................. 11010.3 Confirmation of Scaling Factors for Transient Conditions ..................................................... 11110.4 Scaling Factor Conclusions ................................................................................................... 111

11. SYSTEM AND COM PONENT TESTING REQUIREM ENTS ............................................................ 12611.1 Steam Generator Confirmation Testing ................................................................................. 12611.2 Pressurizer Control Testing ................................................................................................... 12711.3 Natural Circulation Testing ..................................................................................................... 127

11.3.1 Steam Generator Cooling ................................................................................................ 12811.3.2 Emergency Core Cooling System ................................................................................... 12811.3.3 Reactor Coolant Inventory and Purification System Cooling .......................................... 129

11.4 Reactor Coolant System Testing ........................................................................................... 13011.4.1 [ [CCI per Affidavit 4(a) - 4(d)] ...................................... 13011.4.2 [ ] [CCI per affidavit 4(a) - 4(d)] ........ 13111.4.3 [ [CCI per Affidavit 4(a) - 4(d)] ............................................... 131

11.5 Verification of Com ponent, System and Safety Analysis Codes ........................................... 132


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Document No. Title

06-00000392- B&W mPower Tm Reactor001(NP) Integrated Systems Test Technical Report

11.6 System and Com ponent Scaling Issues ................................................................................ 13211.6.1 Stored Energy .................................................................................................................. 13211.6.2 Heat Losses ..................................................................................................................... 133

.11.6.3 Reactor Coolant Pum p .................................................................................................... 13311.6.4 Core/Heaters ................................................................................................................... 133

12. COM PONENT AND SYSTEM S TESTING PROGRAM .................................................................... 1351 2 .1 In tro d u c tio n ............................................................................................................................ 1 3 512.2 IST Testing Section One ........................................................................................................ 13512.3 IST Testing Section Two ........................................................................................................ 13612.4 IST Testing Section Three ..................................................................................................... 13712.5 IST Testing Section Four ....................................................................................................... 13812.6 IST Testing Section Five ........................................................................................................ 13912.7 IST Testing Section Six .......................................................................................................... 140

13. QUALITY ASSURANCE .................................................................................................................... 150

14. REFERENCES .................................................................................................................................. 151

15. ATTACHM ENTS ................................................................................................................................ 152

@2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.Page 7 of 163




List of Figures

Figure 1-1. B&W mPower Reactor and IST Loop Side-by-Side Comparison (425 MWt design) ...... 12Figure 1-2. Center for Advanced Engineering Research with IST Tower in the Foreground ............... 13Figure 1-3. Control Room Panel as viewed through the Window in Data Analysis Room .................... 14Figure 1-4. Operations Staff Office Area .............................................................................................. 15Figure 2-1. Simplified IST Emergency Core Cooling System Line Diagram ........................................ 29Figure 2-2. B&W mPower 425 MWt - IST Loop - 500 MWt Reactor ................................................... 30Figure 2-3. Upgrade System to be Installed with Steam Generator TIC Removal .............................. 31F ig u re 4 -1 . IS T L o o p ................................................................................................................................... 5 6Figure 4-2. IST Core Simulator Cross-Section inside the Vessel .......................................................... 57F ig u re 4 -3 . IS T H e ate r R o d ........................................................................................................................ 5 8Figure 4-4. IST A xial Pow er S hape ....................................................................................................... 59Figure 4-5. IST Core Simulator Cross-Section Showing Thermocouple Locations as Viewed from the

In s e rtio n F la n g e ................................................................................................................. 6 0Figure 4-6. IST Reactor Vessel Assembly ............................................................................................ 61Figure 4-7. IST Steam Generator Arrangement ................................................................................... 62Figure 4-8. IST Tube Support Plate Plan View ..................................................................................... 63Figure 4-9. IST Tube Support Plate Opening Profile ............................................................................ 64Figure 4-10. IST Upper Tubesheet, Riser and Pressurizer Junctions ................................................ 65Figure 4-11. Steam Generator Temperature as a Function of Power Level ........................................ 66F ig u re 4 -12 . IS T P re ss u rize r ...................................................................................................................... 6 7Figure 4-13. IST Downcomer in Pump Region .................................................................................... 68Figure 4-14. Loop Forced Circulation Pump ......................................................................................... 69Figure 4-15. MIST Guard Heater Application ....................................................................................... 70Figure 5-1. Emergency Condenser Vendor Drawing ........................................................................... 81Figure 5-2. B&W mPower Reactor Emergency Condenser Heat Flux ................................................ 82Figure 5-3. IST Emergency Condenser Simulator Heat Flux ............................................................... 83Figure 5-4. Emergency Condenser Outlet Separator ............................................................................ 84Figure 5-5. Configuration for Emergency Condenser E-5001 .............................................................. 85Figure 5-6. Configuration for Emergency Condenser E-5003 ............................................................... 86Figure 5-7. IST Ultimate Heat Sink Tank ............................................................................................... 87F igure 5-8 . H orizontal S pa rger ................................................................................................................... 88F ig u re 5 -9 . V e rtica l S p a rg e r ....................................................................................................................... 8 9Figure 5-10. IST Loop Showing the RWST and Containment Simulation Vessels ............................... 90Figure 9-1. IST C ontrol S ystem D esign .................................................................................................... 103Figure 9-2. IST primary LOOP Trace Heating Regions ........................................................................... 104Figure 9-3. EC C S Trace Heating R egions ............................................................................................... 105Figure 10-1. IST Reactor Pressure Vessel Nodalization .......................................................................... 113Figure 10-2. Cross-section of IST Pressure Vessel Lower End .............................................................. 114Figure 10-3. IST Riser and Pressurizer Nodalization ............................................................................... 115Figure 10-4. IST Steam Generator Nodalization ...................................................................................... 116Figure 10-5. Steam G enerator C ross Section .......................................................................................... 117Figure 10-6. IST D ow ncom er N odalization .............................................................................................. 118Figure 10-7. IST ECCS Primary Side and RWST Nodalization ............................................................... 119Figure 10-8. IST ECCS Secondary Side Nodalization ............................................................................. 120Figure 10-9. IST Heater Rod Heat Structure Nodalization ........................................................................ 121Figure 10-10. IST vs. B&W mPower Comparison of Single Sided Break LOCA Break Mass Flow Rates

......................................................................................................................................... 1 2 2Figure 10-11. IST vs B&W m Power Comparison of Single Sided Break LOCA Pressurizer Pressures.. 123

02011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.Page 8 of 163




Figure 10-12. IST vs B&W mPower Comparison of Single Sided Break LOCA Collapsed Water Levels......................................................................................................................................... 1 2 4

List of Tables

Table 2-1. IST Elevations Relative to B&W mPower Reactor, Relative to Containment Floor ............. 32Table 2-2. Top-Down Scaling Summary ................................................................................................ 33Table 2-3. Figures of Merit for B&W mPower Reactor Design Basis LOCA PIRT ................................ 34Table 2-4. G eneric R isk Perspective ..................................................................................................... 34Table 2-5. B&W mPower Reactor PIRT Risk Perspective Results ...................................................... 35Table 4-1. Vagen Analyses of the Expected Steam Generator Test Points ......................................... 71Table 4-2. Forced Circulation Pump Information ................................................................................ 72Table 5-1. IST Emergency Condenser Design Information ................................................................... 91Table 5-2. Emergency Condenser Performance ................................................................................... 92T a b le 5-3 . P ipe a nd F itting s ....................................................................................................................... 9 3Table 7-1. IST Water Chemistry Control and Diagnostic Parameters ................................................ 97T able 9-1. IST Inventory C ontrol Logic ..................................................................................................... 106T able 9-2 . P ressure C ontrol Logic ............................................................................................................ 106Table 10-1. Achieved Ratio of B&W mPower to IST for 100% Power Steady-State Conditions ............. 125Table 10-2. Achieved Ratio of B&W mPower to IST for 5% Natural Circulation Steady-State

C o n d itio n s ........................................................................................................................ 1 2 5Table 12-1. Projected Testing Sequences ............................................................................................... 141

List of Attachments

Attachment 1 - Integrated Systems Test Primary Loop P&ID, Sheet 1 of 3 ............................................. 153Attachment 2 - Integrated Systems Test Primary Loop P&ID, Sheet 2 of 3 ............................................. 154Attachment 3 - Integrated Systems Test Primary Loop P&ID, Sheet 3 of 3 ............................................. 155Attachment 4 - Integrated Systems Test RWST P&ID, Sheet 1 of 2 ....................................................... 156Attachment 5 - Integrated Systems Test RWST P&ID, Sheet 2 of 2 ....................................................... 157Attachment 6 - Integrated Systems Test RCIP P&ID, Sheet 1 of 2 ......................................................... 158Attachment 7 - Integrated Systems Test RCIP P&ID, Sheet 2 of 2 ......................................................... 159Attachment 8 - Integrated Systems Test Secondary Loop P&ID, Sheet 1 of 1 ........................................ 160Attachment 9 - Integrated Systems Test Instrument Air P&ID, Sheet 1 of 1 ............................................ 161Attachment 10 - Integrated Systems Test Demin & Component Cooling Water P&ID, Sheet 1 of 1 ....... 162Attachment 11 - Integrated Systems Test ECCS P&ID, Sheet 1 of 1 ...................................................... 163



Document No. Title

06-00000392- 1B&W mPower TM Reactor01001(NP) Integrated Systems Test Technical Report

1. OVERVIEW

The Babcock & Wilcox (B&W) mPowerTM reactor is a simplified, modular and passively safe,pressurized water reactor (PWR) nuclear power plant. It uses an integral design for the nuclearsteam supply system, in which the reactor core, control rod drive mechanisms, reactor coolantpump impellers (not motors), pressurizer, and steam generator are contained in a single vessel.The original target power level for the reactor was 425 MWt (125 MWe), but is currently beingoptimized to 500 MWt (160 MWe).

The B&W mPower reactor core utilizes fuel assemblies that are shortened versions of thestandard commercial 17-by-1 7 fuel assembly, and an integral steam generator that is anevolutionary version of the once through steam generators (OTSGs) used in existing B&W-designed operating power reactors.

The integral design of the B&W mPower reactor provides for a large inventory of reactorcoolant, no large external reactor coolant system (RCS) piping, and no reactor vesselpenetrations below the top of the core. The key benefit of these features is the retention ofreactor coolant in the core region of the RCS, such that the reactor core is not uncoveredthrough all design basis events, including loss of coolant accidents (LOCAs).

The B&W mPower reactor design has its roots in integral reactor concepts developed forshipboard applications in the 1960s through the 1970s and secure military power systemsdeveloped in the mid-1 980s. The design most closely resembles the reactor system utilized inthe nuclear merchant ship Otto Hahn.

The purpose of the Integrated Systems Test (IST) program is to extend the existing PWRdatabase to confirm B&W mPower reactor design methodology and to demonstrate that thepassive engineered safety systems and features of the B&W mPower reactor design areadequate to protect the plant and public health and safety. The program is intended to expandand enhance the existing PWR database and add confidence for its application to an integralsystem design. The program is also intended to enhance the database as it relates tocomponent design, build confidence in the nuclear steam supply system and its operation, anddemonstrate the adequacy of plant control systems, engineered safety features, and protectionsystems. Test program data is expected to improve the analytical methodology for, and theunderstanding of, facility design and operation, as well as the application of incorporated safetyfeatures for design basis events. The test facility is expected to provide an understanding of theapplication of abnormal operating procedures and the emergency operating procedures. It mayalso be used in the initial phases of operator training.

IST test procedures are developed based on the analysis of the B&W mPower reactor and thesystem model of the IST simulation using RELAP5. Post-test analyses are used to evaluate thecorrelations selected and the system models used, and to identify whether any new correlationsmay be needed. This also permits an evaluation of the methods available and the ability toapply such methods as the test program advances.


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Figure 1-1 is a side-by-side, scale comparison of the B&W mPower reactor and the IST loop atthe original design power level of 425 MWt. However, as noted above, as the initial designprogressed, it was determined to increase the power level to 500 MWt, with a commensuratelyhigher electrical power output (160 MWe versus 125 MWe).

The IST facility is installed in the Center for Advanced Engineering Research (CAER) located inBedford County just west of Lynchburg, Virginia. Figure 1-2 is a picture of the facility. The ISTloop and emergency core cooling systems are located in the tower except for the ultimate heatsink that has been located on the roof of the tower. The roof is located about 100 feet above thefirst floor. Figure 1-3 is a picture of the operator control panel showing three control stations.The third station has no control capability; however, it will allow the test engineer or others toobserve the test program. The control room is on the ground floor level. The picture was takenfrom the data analysis room. Figure 1-4 is a picture of the operations staff office area in themain facility on the second level or the main facility level based on the front entry to the facility.Offices are provided for the operators, the test engineers, and the IST maintenance staff.

This report describes IST facility functional requirements, systems, the scaling to the 425 MWtdesign, test requirements as currently identified, and a comparison with the power upgradedesign that is in progress. Changes to the facility and/or this report are expected as the B&WmPower reactor design matures and IST program proceeds concurrently. Finally, an overview ofthe test plans is provided concentrating on the first six months of testing.


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Figure 1-2. Center for Advanced Engineering Research with IST Tower in the Foreground





Figure 1-3. Control Room Panel as viewed through the Window in Data Analysis Room





Figure 1-4. Operations Staff Office Area


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Figure 1-4. Operations Staff Office Area


Babcock & Wilcox Nuclear Energy, Inc.a -Babcock & Wilcox company

Document No. Title


2. SCALING

The original IST scaling was based on a 425 MWt B&W mPower integral reactor design.

[CCI per Affidavit 4(a) - 4(d)]

2.1 IST - B&W mPower Reactor Design Features at 425 MWt Power Level

Important features of the B&W mPower reactor design include the following:

I




06-00000392- B&W mPowerTM Reactor001(NP) Integrated Systems Test Technical Report

] [CCI per Affidavit4(a)-4(d)]



Document No. Title

06-00000392-OO1(NP)


2.2 IST - B&W mPower Comparison

The IST primary loop and the scaled B&W mPower reactor at 425 MWt are shown side by sidein Figure 1-1.

] [CCI per Affidavit 4(a)

- 4(d)]

2.3 Top - Down Scaling at 425 MWt

The IST test loop has many objectives, as addressed in Section 3.1. These include confirmationof the design and analysis technology associated with the steam generator and verification ofthe analyses associated with design basis accidents, especially the design basis LOCA. [

©2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.Page 18 of 163


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] [CC[per Affidavit 4(a) - 4(d)]

Due to the diversity of the potential modes that the loop would encounter a simplified top-downapproach was taken based on the paper by Ishii and Kataoka, Reference [1].

2.3.1 Single Phase Natural Convection

I


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] [CCI per Affidavit 4(a) - 4(d)]

2.3.2 Scaling Anomalies

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2.3.3 Top down Scaling Conclusions

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2.3.4 Assessment of Applicability of IST to Power Upgrade

The design power level of the B&W mPower reactor has been increased from the initial 425MWt to 500 MWt with the continued plant optimization. A side by side comparison of the 425MWt reactor, the IST loop, and the power upgrade level are shown in Figure 2-2. Along with theincrease in power level, several other changes have been made. These changes include:

] [CC[ per Affidavit 4(a) - 4(d)]

2.3.4.1 IST Scale Factor Change for Power Upgrade

I

] [CCI per Affidavit 4(a) -4(d)]



Document No. Title


2.3.4.2 Core & System Upgrades

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2.3.4.3 IST Power Upgrade Scaling Conclusions

I


2.4 Bottom-Up Scaling at 425 MWt

As part of the conceptual design process, a phenomena identification and ranking table (PIRT)was developed for the design basis LOCA for the B&W mPower reactor system. [

[CCI perAffidavit 4(a) - 4(d)]





A Figure of Merit (FOM) is the criterion against which the Relative Importance of each"phenomenon" is judged. Successful figures of merit have distinct characteristics as follows:

" directly related to the issue (Step1)

* directly related and explicit to the phenomena identified

* easily comprehended

* measurable

The FOMs determined to be most appropriate for the objectives of this PIRT are shown in Table

2-3.

2.4.1 Safety Related Risk Perspective

In the context of the PIRT, a Risk Perspective relates to the relative uncertainty inunderstanding the combined Relative Importance and State of Knowledge (SOK) of aphenomenon. For example, a phenomenon which is controlling in the reactor response to apostulated accident scenario (high Relative Importance) and has a large or undetermined SOK(low SOK) poses the highest level of risk in understanding the safety significance of thatphenomenon. Further, a phenomenon having a high Relative Importance and moderate SOKposes the next relative level of risk, and so on through decreasing levels of risk. The generic riskperspective applicable to this PIRT is described in Table 2-4.

The risk perspective of most interest to the B&W mPower safety related licensing and regulationactivities adequately captured by considering the PIRT results for the first three risk levels.Those results are summarized in Table 2-5, including potential research that may have promisein further reductions in the risk.

2.4.2 Components that Dominate Each LOCA Phase

The components that dominate the various phases have been identified and delineated in Table2-5. The characteristics of the components that contribute to this dominance are discussed inthis section.

* Subcooled Blow Down - Phase 1

I

I [CCI perAffidavit 4(a) - 4(d)]





. Saturated Two-Phase Blow Down - Phase 2

I

] [CCI perAffidavit 4(a) - 4(d)]

0 Saturated Steam Blow Down to ADS Actuation - Phase 3

[


. Depressurization to Passive RWST Makeup - Phase 4

I


0 Long Term Cooling to 72 Hours - Phase 5

I






2.4.3 Recommendations for B&W mPower Reactor Use of PIRT Results

The ECCS design is in the process of being finalized and the analyses of the selected designbasis LOCA is ongoing. On this basis the PIRT may need to be revisited when the design isfinalized. Based on the state of the design an analysis through November 2010 and the reviewby the team of experts the following conclusions can be made:


2.4.4 Assessment of PIRT Recommendation Relative to Power Upgrade

A review of the phenomena identified and evaluated during the LOCA PIRT process wasreviewed, resulting in these observations:

[


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I


Figure 2-1. Simplified IST Emergency Core Cooling System Line Diagram

©2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

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I

I

[CCI per Affidavit 4(a)-4(d)]

Figure 2-2. B&W mPower 425 MWt - IST Loop - 500 MWt Reactor

Q2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.Page 30 of 163




I


Figure 2-3. Upgrade System to be Installed with Steam Generator TIC Removal





Table 2-1. IST Elevations Relative to B&W mPower Reactor, Relative to ContainmentFloor

Component IST B&W mPower Reactor

Bottom heated length

Top of heated Length

Riser Flow over elevation

Top of upper tubesheet

Bottom of upper tubesheet

Top of lower tubesheet

Bottom of lower tubesheet

Bottom pressurizer separator plate

Normal pressurizer water level

Top pressurizer stand pipe(s)

Bottom Pressurizer head

Centerline break

Break inlet elbow

Water level in RWST

Centerline emergency condenser

Bottom of ultimate heat sink (UHS) tanks

Water Level in UHS



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Document No. Title

06-00000392-001(NP)

B&W mPower Tm ReactorIntegrated Systems Test Technical Report

Table 2-2. Top-Down Scaling Summary

Scaling Group Single-Phase Two-Phase

I

i i

I +

i +

4 +

I -~

4 +

4-i

±

.4-

+

[C~lper

ffidvit (a)-(d)

[cci per Affidavit 4(a)-4(d)]





Scaling Group Single-Phase Two-Phase


Table 2-3. Figures of Merit for B&W mPower Reactor Design Basis LOCA PIRT

PHASE Figure of Merit Interval

[


Table 2-4. Generic Risk Perspective

Risk Phenomena Phenomena Probable ResponseLevel Relative State Of To Reduce

Importance Knowledge Risk



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Table 2-5. B&W mPower Reactor PIRT Risk Perspective Results

Phase &Risk System Phase- SOK Comments Related To PotentialLevel Component Importance Rank Risk ReductionevlPhenomenaRak________________

Rank

[CCl per Affidavit 4(a)-4(d)]


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Phase &Risk System Phase- SOK Comments Related To PotentialLevel Component Importance Rank Risk ReductioneelPhenomenaRak_______________

Rank

[CCl per Affidavit 4(a)-4(d)]





Phase &Risk System Phase- SOK Comments Related To PotentialLevel Component Importance Rank Risk Reduction

eelPhenomenaRank



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Document No. Title

06-00000392- 1B&W mnPower TM Reactor 001001(NP) Integrated Systems Test Technical Report

3. FUNCTIONS AND DESIGN REQUIREMENTS

3.1 Functions

The IST program is designed to evaluate the inherent safety margins associated with the B&WmPower integral reactor design and associated passive engineered safety features.

3.1.1 Steam Generator Characteristics

[CCI per Affidavit 4(a) - 4(d)] The IST program is intended to extend the existingdatabase and provide confidence in the correlations used to cover the operating range of theB&W mPower reactor steam generator.

3.1.2 Design Basis Event Testing

The B&W mPower reactor contains all the RCS components in a single vessel, which enhancesthe reactor response to operational transients and design basis events, including takingadvantage of passive engineered safety features. [

] [CCI per Affidavit 4(a) - 4(d)] The reactorcore is located at the bottom of the reactor vessel and the pressurizer is at the top of the reactorvessel. The steam generator surrounds the central riser within the reactor vessel, below thepressurizer. The reactor coolant pumps are located in the downcomer annulus just below thesteam generator. The IST program is intended to develop the required data to support thesafety analysis methodology used in the design certification application for the B&W mPowerreactor and to demonstrate that the B&W mPower reactor protection systems and engineeredsafety features are sufficient to protect the plant and public health and safety.

3.1.3 Operational Testing

The IST program is intended to confirm the operational characteristics of the B&W mPowerreactor systems and the associated control and protection systems.

3.1.4 Flow Characteristics

The IST program is intended to confirm the methodology used in the design of the B&WmPower reactor system and transitions to the various states associated with natural circulationcooling and reactor coolant makeup.



Document No. Title

06-00000392-OO1(NP)


3.2 Reactor Coolant System Desigqn Requirements

3.2.1 ASME Code Design Requirements

IST loop vessels are designed and stamped based on ASME Boiler and Pressure Vessel Code(ASME Code), Section VIII UG-99, 2007 Edition, up to and including 2009 Addenda, and ISTloop piping to ASME B31.1.

The IST loop also incorporates additional requirements as required by ASME Code Section Iand any other unique requirements for installation in the state of Virginia.

The IST loop is protected with one or more ASME Code approved safety valves.

The steam generator steam outlet is protected with one or more ASME Code approved safetyvalves inside the steam line isolation valve, taking into account the rupture of a steam generatortube.

All activities including design, fabrication, procurement, inspection and code stamping areperformed to B&W Nuclear Energy Quality Assurance Program procedures and standards, withASME Code documents and supporting calculations and documents provided with theequipment.

3.2.2 IST Reactor Loop Design Requirements

The IST design was based on scaling the B&W mPower integral reactor producing 425 MWt.Subsequently, the B&W mPower integral reactor thermal output has been optimized to 500MWt. IST design parameters for the scaled optimized power level are shown in parenthesis.


Page 39 of 163


hDocument No.

06-00000392-001(NP) 1= Title


I[CCI per Affidavit 4(a) - 4(d)]

3.2.3 Instrumentation Requirements

] [CCI per Affidavit 4(a) - 4(d)] The required ranges for theinstrumentation are provided in Sections 3.2.3.1 through 3.2.3.5.

System and component instrumentation for the IST facility is more extensive than that for theB&W mPower reactor systems instrumentation for several reasons:

1. For testing of the control system and any new algorithm that may be used in normaloperation to allow an expansion in the normal operational boundaries and reactorapplications.

2. To allow component design related testing.

3. To cover protection system and engineered safety feature testing.

4. For methodology development and testing for design and analysis of the integral reactorsystems and components.

5. For operator training and system behavior understanding, including abnormal operationand emergency operation.

6. The controls for the pump will allow both constant speed and constant mass flow.


Page 40 of 163


I Document No. Title

06-00000392-0O1(NP)


3.2.3.1 IST Loop Control and Protection Systems

I



Document No. t Title

06-00000392-001(NP)


][CCl per Affidavit 4(a) - 4(d)]

3.2.3.2 Engineered Safety Features

Emergency Core Cooling System

I

I[CCl per Affidavit 4(a) - 4(d)]

3.2.3.3 Steam Generator

[


Page 42 of 163





3.2.3.4 Pressurizer

I


3.2.3.5 Riser


3.2.4 Reactor Protection System and Engineered Safety Feature Activation Test

Requirements

[






3.3 Core Simulation

I






4. SYSTEM DESCRIPTION

The IST facility is designed to confirm B&W mPower reactor design basis methodology anddemonstrate that the passive engineered safety systems of the B&W mPower reactor areadequate to protect the plant and public health and safety.



Document No. Title

06-00000392-001(NP)



4.1 Core Simulator

4.1.1 Core and Core Internals/Support


4.1.2 Core Simulator Heaters

[



Document No. Title

06-00000392-001(NP)


I[CC[ per Affidavit 4(a) - 4(d)]

4.1.3 Reactor Vessel

The IST reactor vessel is constructed from



Page 47 of 163




4.1.4 Power Supply

I

] (CCI per Affidavit 4(a) - 4(d)]

4.2 Steam Generator

I



Page 48 of 163




4.2.1 Tubes

[


4.2.2 Shroud

[


4.2.3 Tube Support Plates

I


Page 49 of 163


hDocument No. t Title

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4.2.4 Tubesheets

I


4.2.5 Steam Generator Instrumentation

[



Page 50 of 163


Document No. Title


4.2.6 Tube Rupture Simulation


4.3 Pressurizer

I


4.3.1 Vessel

[


4.3.2 Baffle Plate and Surge Arrangement

I


4.3.3 Spray






4.3.4 Heaters


4.3.5 Instrumentation


4.3.6 Code Safety Valves

[


4.4 Reactor Coolant Pump Region Simulator

I


Page 52 of 163




] [CCI per Affidavit 4(a) -

4(d)]

4.5 Other Reactor Coolant System Pipe Sections

4.5.1 Riser

4.5.1.1 Control Rod Drive Segment


4.5.1.2 Steam Generator Segment

I


4.5.2 Steam Generator/Pressurizer/Riser Junction

[


Page 53 of 163





4.5.3 Pump-Steam Generator to Reactor Vessel


4.5.4 Reactor Coolant Support Loop

I


4.6 Loop Insulation

[


Page 54 of 163


Document No. Title

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] [CCIper Affidavit 4(a) - 4(d)]


Page 55 of 163


Document No. Title

06-00000392-O01(NP)


L- -

I


Figure 4-1. IST Loop



Document No. Title


I

]


Figure 4-2. IST Core Simulator Cross-Section inside the Vessel


Page 57 of 163




[

I

[CCI per Affidavit 4(a) - 4(d)]Figure 4-3. IST Heater Rod


Page 58 of 163




[

r T 1

-~ 1* 1~

1- 1-~

I I +

.2

00.

Axial Position (m)] [CCI per Affidavit 4(a) - 4(d)]

Figure 4-4. IST Axial Power Shape


Page 59 of 163





Figure 4-5. IST Core Simulator Cross-Section Showing Thermocouple Locations asViewed from the Insertion Flange






Figure 4-6. IST Reactor Vessel Assembly


Page 61 of 163




I

][CCI per Affidavit 4(a) - 4(d)]

Figure 4-7. IST Steam Generator Arrangement


Page 62 of 163


Document No. Title


[

I


Figure 4-8. IST Tube Support Plate Plan View



Document No. Title


I

I


Figure 4-9. IST Tube Support Plate Opening Profile


Page 64 of 163




]


Figure 4-10. IST Upper Tubesheet, Riser and Pressurizer Junctions





I

I


Figure 4-11. Steam Generator Temperature as a Function of Power Level



Document No. Title

06-00000392-0O1(NP)


I

I

Figure 4-12. IST Pressurizer[CCI per Affidavit 4(a) - 4(d)]


Page 67 of 163


Document No. Title

06-00000392-0O1(NP)


I


Figure 4-13. IST Downcomer in Pump Region


Page 68 of 163




I


Figure 4-14. Loop Forced Circulation Pump


Page 69 of 163




I

I


Figure 4-15. MIST Guard Heater Application


Page 70 of 163




Table 4-1. Vagen Analyses of the Expected Steam Generator Test Points

_____ I. __ __ II __ __ __ I __ I __

____ I __ __ __ __ I __ I __ __ __ I __

4 4 4 I 4 I I I 4.

1~ V V I

1 4 4 4 4. I I 4 4.

I 4 4 4 4. 4 4 4 4.

1 4 4 4 4 4 4 4 4.

1 4. 4. 4 4 4 4 4 4

4 4. 4. 4 4 4 4

4 4. 4. 4 4 4 4 4. I

4 4. 4. 4 4 4 4. 4. I

4 4. 4. 4 4 4 4. 4. I

4 + 4. 4. 4 4 4. 4~ I

4 4. 4. 4. I 4. 4. 4. t

4 4 4. 4. I 4. 4. 4. I

4 4 4 4. I 4. 4. 4. I



Page 71 of 163


Document No. Title


Table 4-2. Forced Circulation Pump Information

I




Document No. Title

06-00000392-001(NP)


5. ENGINEERED SAFETY FEATURE COMPONENTS AND DECAY HEAT REMOVAL

5.1 Emergency Core Cooling Trains

I

I [CCI per Affidavit 4(a) - 4(d)]

5.1.1 Emergency Condenser Cooling

I


Page 73 of 163





5.1.2 Separator at Emergency Condensed Condensate Outlet



Page 74 of 163


Document No. Title

06-00000392-O01(NP)


5.1.3 Automatic Depressurization Valves


5.1.4 ECC Piping & Valves

I


5.1.5 ECCS Insulation

The ECC trains are covered with insulation and trace heating to limit the loss of energy to theenvironment for long term cooling events

5.1.6 Ultimate Heat Sink




06-00000392- B&W mPowerTM Reactor 001001(NP) Integrated Systems Test Technical Report


5.1.7 UHS - Emergency Condenser Feedwater Pipe

I

per Affidavit 4(a) - 4(d)]

5.1.8 UHS - Emergency Condenser Return Piping


5.1.9 ECCS Spargers

I

][CCl


5.1.10 Pipe Insulation and Support

[



Page 76 of 163




5.2 Emergency Boron System


5.3 Steam Generator Steam Vent,


5.4 RWST and Containment

The RWST containment simulation is illustrated in Figure 5-10. The IST RWST is



Document No.

06-00000392-001(NP)

Title


L-


Attachments 4 and 5 are the P&IDs for the RWST system.

5.5 Steam and Feed Component

The ability to steam and feed for core cooling is provided in the IST.

Affidavit 4(a) - 4(d)]

5.6 Reactor Coolant Inventory and Purification Subsystem

[

] [CCI per






Page 79 of 163


KDocument No.

06-00000392-001(NP)

Title



Attachments 6 and 7 are the P&IDs for the RCIPS.


Page 80 of 163




I


Figure 5-1. Emergency Condenser Vendor Drawing


Page 81 of 163




I

[CCl per Affidavit 4(a) - 4(d)]

Figure 5-2. B&W mPower Reactor Emergency Condenser Heat Flux


Page 82 of 163



06-00000392- B&W mPower TM Reactor 0010O1(NP) Integrated Systems Test Technical Report

I


Figure 5-3. IST Emergency Condenser Simulator Heat Flux


Page 83 of 163




[


Figure 5-4. Emergency Condenser Outlet Separator





I

]


Figure 5-5. Configuration for Emergency Condenser E-5001



Document No. Title

06-00000392-001(NP)


I


Figure 5-6. Configuration for Emergency Condenser E-5003


Page 86 of 163


Document No. Title


II

]


Figure 5-7. IST Ultimate Heat Sink Tank





I


Figure 5-8. Horizontal Sparger





[

I


Figure 5-9. Vertical Sparger





I

[CCI per Affidavit 4(a) - 4(d)]Figure 5-10. IST Loop Showing the RWST and Containment Simulation Vessels





Table 5-1. IST Emergency Condenser Design Information



Page 91 of 163




Table 5-2. Emergency Condenser Performance

I



Page 92 of 163


Document No. Title

06-00000392-0O1(NP)


Table 5-3. Pipe and Fittings

I

I. I-

*1-

i +

i +

t t 1- t

I



Page 93 of 163




6. COMPONENT COOLING WATER SYSTEM


6.1 RCIPS Heat Exchan-gers Coolinq

Cooling water is provided [


6.2 Loop Pump Cooling

[] [CCI per Affidavit 4(a) - 4(d)]

6.3 Heater Rod Seal Coolinq

I



Page 94 of 163




6.4 Feedwater Purification Heat Exchanger Cooling

I



Page 95 of 163




7. STEAM, FEEDWATER, AND CONDENSATE SYSTEMS

I


Attachment 8 is the P&ID for the steam, feedwater, and condensate systems.



Document No. Title


Table 7-1. IST Water Chemistry Control and Diagnostic Parameters

I

I4

I

][CCI per Affidavit 4(a) - 4(d)]





8. INSTRUMENTATION FOR CONTROL, PROTECTION, AND DATA ACQUISITION

[



Page 98 of 163




9. CONTROL, PROTECTION, AND DATA ACQUISITION SYSTEMS

The IST uses a DeltaV PlantWeb control system. The architecture of the DeltaV systemprovides integration of "smart" bus technology, including Foundation FieldBus, ProfiBus DP,DeviceNet, AsiBus, Ethernet and serial connections. The system includes integrated timesynchronization and the ability to time-stamp data at the lowest level of the architecture.

The DeltaV software is used for field device calibrations, replacement, record keeping,diagnostics and testing. The DeltaV global database includes security, historian with data"status," event capture, process alarm management, field device alerts and system diagnostics.The DeltaV configuration and version control audit trail allows version control and changemanagement to the global database. The offline simulation environment of the DeltaV systemprovides the ability to build medium- to high-process models with the DeltaV configuration as isemployed in the test environment.

The IST facility control system incorporates a secure engineering and operational environment,including services for communications, alarming, operator graphics, system diagnostics, planthistorian and engineering. The system consists of a dedicated process controller; and providesa streamlined flow of diagnostic information and communication. The system also has thecapability of supporting basic and advanced process control functions and any combination ofinput/output subsystems, including conventional, digital and wireless. Data from instrumentsthroughout the IST are recorded at a 1-sec sampling rate. Figure 9-1 illustrates the architecturefor the control, protection and data acquisition system.

A reliable air system using two full-capacity compressors supplies the instrument air to thecontrol devices.

Attachment 9 is the P&ID for the instrument air system.

9.1 Loop Inventory Control - RCIPS

9.1.1 Fixed Level Band Control

[CCI per


9.1.2 Level Band Floats with Power Level


Page 99 of 163





9.2 Loop Pressure Control

I


9.3 Loop Flow Control

] [CCI per


9.4 Heater/Core Power Control

I

] [CCI per Affidavit4(a) - 4(d)]

9.5 Trace Heater Control






The region breakdown for the primary loop heat tracing is shown in Figure 9-2, and thebreakdown for the ECCS are given in Figure 9-3.

9.6 Reactor Protection and Engineered Safety Feature Activation Systems

[


9.6.1 Reactor Protection System Setpoints for 425 MWt Equivalent Testing

I


Page 101 of 163


Document No. Title



9.6.2 Engineered Safety Feature Activation System Setpoints

I


9.6.3 Additional Loop Protection

The ASME Code B&W mPower requirements are spelled out in Section 3.2.1 under coderequirements. The minimum ASME Code sections I and VIII are required for IST. The ASMECode approved pressure relief valves for IST are large compared to the loop design flows andvolumes.



Page 102 of 163





Figure 9-1. IST Control System Design


Page 103 of 163


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[

I


Figure 9-2. IST primary LOOP Trace Heating Regions


Page 104 of 163


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I


Figure 9-3. ECCS Trace Heating Regions


Page 105 of 163




Table 9-1. IST Inventory Control Logic

[

4 i

4 +

4 +

4 4

* 4

i i

Table 9-2. Pressure Control Logic

I



Page 106 of 163




10. IST - B&W MPOWER REACTOR RELAP5 ANALYSES AT 425 MWT

B&W NE is developing RELAP5 models of the IST. These models will be used for comparingRELAP5 results with data collected from the IST test. [


This section is divided into three topics. The first summarizes the IST RELAP5 model. Thesecond documents the steady-state comparisons of the IST and B&W mPower model. Thethird documents the transient comparisons of the IST and B&W mPower model. Currently, boththe IST and the B&W mPower RELAP5 models are in a state of development so these resultsshould be considered preliminary.

10.1 IST Modeling for RELAP5

The purpose of this section is to provide a description of the IST model used for preliminaryscaling comparisons. The model presented here is preliminary based on information availableat the time. However, the model has been documented and checked for accuracy and isadequate for the purposes of this preliminary scaling comparison. Prior to making pre-testpredictions, it is expected that a number of changes will be made to reflect the as-built plant andto align with best practices for PWR plant modeling.

The objective of this section is to provide a description of the RELAP5 modeling of ISTcomponents. A detailed description of IST systems and components has been provided inSections 4, 5, 6, and 7. Figures provided are representative of the relationship betweensystems and components of the IST and corresponding RELAP5 models. The following parts ofthe IST have been incorporated into this preliminary model.

[


Page 107 of 163





10.1.1 Reactor Pressure Vessel

I


10.1.2 Steam Generator


10.1.3 Pressurizer




Document No. Title


10.1.4 Riser


10.1.5 Downcomer

I


10.1.6 Emergency Core Cooling Systems

I



Document No. Title

06-00000392-001(NP)


] [CCI per Affidavit4(a) -4(d)]

10.1.7 Heat Structures

Heat structure models are solid structures that generate heat, conduct heat betweenliquid/vapor volumes, and stores/releases energy with changes in system temperatures.


10.1.7.1 Heater Rods

I


10.1.7.2 Heat Transfer Structures

per Affidavit 4(a) - 4(d)]] [CCI

10.2 Confirmation of Scaling Factors at Steady State Conditions


Page 110 of 163





10.3 Confirmation of Scaling Factors for Transient Conditions

p

per Affidavit 4(a) - 4(d)]][CCI

10.4 Scaling Factor Conclusions

This section has shown that the scaling approach and the various design compromises toreduce atypicalities in the IST have resulted in similar SS and transient performance betweenB&W mPower and the IST. This is an important step in the overall testing and safety analysiscode qualification program. The next stage of the RELAP5 model development will further



Document No. Title Rev. l'


enhance the model with as-built design dimensions and prepare the model to make pre-testpredictions of the IST transient performance.





I


Figure 10-1. IST Reactor Pressure Vessel Nodalization





[

I


Figure 10-2. Cross-section of IST Pressure Vessel Lower End



Document No. Title

06-00000392-001(NP)


I

[


Figure 10-3. IST Riser and Pressurizer Nodalization





I

I


Figure 10-4. IST Steam Generator Nodalization




06-00000392- B&W mPower TM Reactor 0010O1(NP) Integrated Systems Test Technical Report

I


Figure 10-5. Steam Generator Cross Section



Document No. Title

06-00000392-001(NP)


I


Figure 10-6. IST Downcomer Nodalization



Document No. Title

06-00000392-001(NP)


II

I


Figure 10-7. IST ECCS Primary Side and RWST Nodalization





I


Figure 10-8. IST ECCS Secondary Side Nodalization



Document No. Title

06-00000392-OO1(NP)


I


Figure 10-9. IST Heater Rod Heat Structure Nodalization



Document No. Title

06-00000392-001(NP)


I

I


Figure 10-10. IST vs. B&W mPower Comparison of Single Sided Break LOCA Break MassFlow Rates



Document No. Title

06-00000392-001(NP)


[

]


Figure 10-11. IST vs B&W mPower Comparison of Single Sided Break LOCA PressurizerPressures


Page 123 of 163


Document No. Title

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[

]


Figure 10-12. IST vs B&W mPower Comparison of Single Sided Break LOCA CollapsedWater Levels



Document No. Title

06-00000392-001(NP)


Table 10-1. Achieved Ratio of B&W mPower to IST for 100% Power Steady-StateConditions

I

___ + 4 i

___ + 4 +

-4- 4 +

4 4 +

___ + 4 +

I


Table 10-2. Achieved Ratio of B&W mPower to IST for 5% Natural Circulation Steady-State Conditions

I

i- ii

t I* I. .4

I






11. SYSTEM AND COMPONENT TESTING REQUIREMENTS

IST program system and component testing supports computer software development andverification, component and system model development and verification, and control andprotection system development. The testing supports safety analysis, licensing anddevelopment of abnormal and emergency operating procedures. The testing providessupporting data for system transients associated with various operational occurrences anddesign basis events as they transition from various operating points to a stable long-termcooling state. The tests are also broad in scope, to provide a better overall understanding ofcomponent performance, system performance, systems interaction, control system design, andprotection system design.

The B&W MIST program was a set of tests conducted in the mid-1 980s, following the TMI-2accident, which related largely to the understanding of small break LOCAs (Reference 6). TheIST program is patterned after the MIST program, with an expanded scope to document B&WmPower reactor integral plant performance over a full spectrum of normal and transientoperating conditions.

11.1 Steam Generator Confirmation Testing


Page 126 of 163





11.2 Pressurizer Control Testing

I


11.3 Natural Circulation Testing



Page 127 of 163


Document No. Title


11.3.1 Steam Generator Cooling

Affidavit 4(a) - 4(d)]][CCI per

11.3.1.1 Normal Single-Phase Cooling


11.3.1.2 Saturated Two-Phase Cooling RCS Level in Tube Region

I


11.3.1.3 Boiler Condenser Cooling

I


11.3.2 Emergency Core Cooling System

I


11.3.2.1 Emergency Condenser Subsystem



[.Document No.

06-00000392-001(NP)

Title



11.3.2.2 Reactor Coolant System Steam and Feed Cooling

I

[CCIper Affidavit 4(a) - 4(d)]

11.3.3 Reactor Coolant Inventory and Purification System Cooling

The B&W mPower reactor RCIPS serves a number of functions, as described in Section 5.6.

I


Page 129 of 163




[CCI per Affidavit4(a) - 4(d)]

11.4 Reactor Coolant System Testinq

Sections 11.4.1 through 11.4.3 summarize planned IST testing for the RCS.

11.4.1 [ ] [CCI per Affidavit 4(a) - 4(d)]


Page 130 of 163




11.4.2 [


] [CCI per affidavit 4(a) - 4(d)]


] [CCI per Affidavit 4(a) - 4(d)]11.4.3 [


Page 131 of 163





11.5 Verification of Component, System and Safety Analysis Codes

[


11.6 System and Component Scaling Issues

11.6.1 Stored Energy

I



Page 132 of 163


Document No. Title


11.6.2 Heat Losses


11.6.3 Reactor Coolant Pump

I


11.6.4 Core/Heaters


Page 133 of 163


Document No. Title

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Document No. Title

06-00000392-001(NP)


L-- -

12. COMPONENT AND SYSTEMS TESTING PROGRAM

The existing fleet of commercial reactors was based on a large number of component tests thatwere integrated analytically. The B&W Multi Loop Integral Systems Test (MIST) [11] was a setof follow on tests that related largely to the understanding of the small break loss of coolantaccident.

[CCI per Affidavit

4(a) - 4(d)]

12.1 Introduction

[CCI per Affidavit 4(a) - 4(d)] Each section oftesting will be described below. The projected test sequence is shown as Table 12-1.

12.2 IST Testinq Section One

I



Document No. Title

06-00000392-001(NP)



12.3 IST Testing Section Two

I



Document No. t Title

06-00000392-001(NP)


] [CCl per Affidavit 4(a) - 4(d)]

12.4 IST Testing Section Three

I






12.5 IST Testing Section Four

[


Page 138 of 163


Document No. Title

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12.7 IST Testing Section Six

I




Document No. Title



12.6 IST Testing Section Five

[


Page 139 of 163


Document No. Title

06-00000392-001(NP)


Table 12-1. Projected Testing Sequences

I

~1 _______

i1 i

+ i

+ +

+ 4

+ 4

4 4

4- 4

4 4


Page 141 of 163


Document No. Title


+

.4- 4

+ 4

-4- +

+ +

-4- 4

i i

i

4. .

4. 4-

4 .4.

4 .4.

4 +





i 'i

i4-

i +

+ +

*1*

4 +

4 +

4 *

.9 I.

-i

4 4

I I


Page 143 of 163



06-00000392- B&W mPower TM ReactorO01(NP) Integrated Systems Test Technical Report

+ 4

+ 4

4 4

I 4

4 +

-p

4 +

4 1-

I .1-

4 +

4 4

4 4

4 4





I- r

+ I

+ I

4- 4

+ I

+ I

+ 4

4 4

I. 4

i i

1 4

4-

- a


Page 145 of 163



06-00000392- B&W mPowerTM Reactor 001001(NP) Integrated Systems Test Technical Report

I. .4

I. .4

L 4.

1-

+

4 .4-

4 +

4 4

4 4

4 i.

i i

.4 I.

.4 i

.4 1






Page 147 of 163




4- r

4-

+ t

4. 4

.4. 4

* 4

.4. 4

4

4. 4

I 4

I. .1

I. I

I 4

4 -I.

4 4.

4 +

4 4.

4 +

4 4-

4 .4.





*1- T

+ *

+ 4

+ 4

4 i

-p

-p

I



Page 149 of 163


Document No. Title


13. QUALITY ASSURANCE

The IST program is a significant part of the B&W mPower reactor design verification program.The IST program is conducted in accordance with the "Quality Assurance Program for theDesign Certification of the B&W mPower Reactor TM ," as described in B&W Topical Report(Reference 9).

Key quality assurance elements of the IST program include design verification by testing, testcontrol, and control of measuring and test equipment. The IST program is conducted inaccordance with written procedures, and the IST facility is operated by trained operatorspursuant to approved procedures.

A RELAP5 model of the integral reactor test loop and supporting systems is used to verifyscaling and to predict the results of the tests for comparison to expected plant performance, andto provide a basis for establishing acceptance criteria. Means to verify the accuracy of data areestablished, such as redundant instrumentation or related instrumentation. Judgment as to thequality of the data is made prior to signing off on test completion.

It is recognized that plant design, IST systems design, and test program design are beingconducted concurrently. Wherever possible, flexibility in the IST program design is incorporated.


Page 150 of 163




14. REFERENCES

1. Ishii, M. and I. Kataoka, "Scaling Criteria for LWR's under Single-Phase and Two-PhaseNatural Circulation." Presented at Joint NRC/ANS Meeting on Basic Thermal HydraulicMechanisms in LWR Analysis, September, 1982, Bethesda, MD

2. Marks' Standard Handbook for Mechanical Engineers, Eighth Edition, McGraw-Hill BookCo., New York, 1978, p. 13-79.

3. Handbook of Hydraulic Resistance, 3rd Edition, I.E. Idelchik, Jaico Publishing House,Delhi, 2008.

4. Flow of Fluids Through Valves, Fittings and Pipe, Technical Paper 410, Crane Co.,Stamford, CT, 2009.

5. Two-Phase Flow, Boilinq and Condensation in Conventional and Miniature Systems,Ghiaasiaan, S. Mostafa, Cambridge University Press, New York, 2008, p. 233.

6. "Multiloop Integral Systems Test (MIST): Final Report, Summary," Gloudemans, James

R., NUREG/CR-5395, EPRI/NP-6480, BAW-2023 Volume 1, April 1991.

7. Heat Transfer Research Institute, Inc. (HTRI) HTRI Xchanger Suite 6.

8. PWR Primary Water Guidelines, Volume 1, Revision 4. TR-105714-V1R4.

9. "Quality Assurance Program for the Design Certification of the B&W mPowerTM ReactorTopical Report," 08-00000320-000-A, Revision 2, N-RO01 5, January 2011.





15. ATTACHMENTS

1. Integrated Systems Test Primary Loop P&ID, Sheet 1 of 3.



4. Integrated Systems Test RWST P&ID, Sheet 1 of 2.

5. Integrated Systems Test RWST P&ID, Sheet 2 of 2.

6. Integrated Systems Test RCIP P&ID, Sheet 1 of 2.

7. Integrated Systems Test RCIP P&ID, Sheet 2 of 2.

8. Integrated Systems Test Secondary Loop P&ID, Sheet 1 of 1.

9. Integrated Systems Test Instrument Air P&ID, Sheet 1 of 1.

10. Integrated Systems Test Demin & Component Cooling Water P&ID, Sheet 1 of 1.

11. Integrated Systems Test ECCS P&ID, Sheet 1 of 1.


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