ML21175A247
| ML21175A247 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Summer, Surry, North Anna  |
| Issue date: | 06/24/2021 |
| From: | Mark D. Sartain Dominion Energy Nuclear Connecticut, Dominion Energy South Carolina, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 21-183 | |
| Download: ML21175A247 (42) | |
Text
Dorninion 5000 omno ou vard e Allen,VA 23060 DominionEnergy.com bR@@f June24,2021 10CFR50.46 U.S.
Nuclear Regulatory Commission Serial No.:
21-183 Attention
- Document Control Desk NRA/CLT RO Washington, DC 20555 Docket Nos.:50-336/423 50-338/339 50-280/281 50-395 License Nos.:DPR-65/NPF-49 NPF-4/7 DPR-32/37 NPF-12 VIRGINIA!ELECTRIC ANDPOWER COMPANY MILLSTONE POWERSTATIONUNITS2AND 3 NORTHANNAPOWERSTATIONUNITS1AND 2 SURRYPOWERSTATIONUNITS1AND2 VIRGILC.S.UMMER
'NUCLEAR STATIONUNIT1 Inaccordance with010 CFR50.46(a)(3)(ii),
Dominion Energy Nuclear Connecticut, Inc.
(DENC),
Virginia El6ctric andPowerCompany(Dominion Energy Virginia),
andDominion EnergySouthGarolina, Inc.(DESC) hereby submit theannual summary ofpermanent changes to)the semergency corecooling system(ECCS) evaluation models (EMs) for Millstone Power:StAtion (MPS)
Units 2and3,North AnnaPowerStation (NAPS) Units1 and2,SurryPower Station (SPS)
Units 1and2,andVirgil C.Summer Nuclear Station (VCS)
Unitt1,Jrespectively.
Attachment 1,ofsthis' I,etter provides a report describing plant-specific evaluation model changes associat'ed/with theWestinghouse andFramatome Small Break LossofCoolant Accident (SBLOCA) andLargeBreakLossofCoolant Accident (LBLOCA)
ECCSEMs forMPS2and13,-NAPS 1and2,SPS1and2,andVCS1,as'applicable.
Information regarding theeffect oftheECCSEMchanges uponthereported SBLOCA andLBLOCA,analyses ofrecord results isprovided forMPS2and3,NAPS1and2,SPS 1and2,and'VCS1dinAttachments 2,3,4and5,respectively.
Thecalculated peak cladding temperatures (PCT) fortheSBLOCAandLBLOCAanalyses forMPS2and3, NAPS1and2,nSPS1and2,andVCS1aresummarized below:
Millstone Unit 2
Small break
- Framatome EM:
1714F Millstone Unit 2
Largebreak
18450F Millstone Unit 2
Large break
16150F ff
Serial No.21-183 Docket Nos.50-336/423/338/339/280/281/
2020Annual 10CFR50.46 Report Page2of4 Millstone Unit 3 Small break
- Westinghouse EM:
11930F Millstone Unit 3 Large break
- Westinghouse EM:
19330F North Anna Units 1and2 Small break
- Westinghouse EM:
1834.10F North AnnaUnits 1and2 Large break
- Westinghouse EM:
1982F Surry Units 1and 2 Small break
- Westinghouse EM:
2012F Surry Units 1and2 Large break
- Westinghouse EM:
20710F Virgil C.SummerUnit 1 Smallbreak
- Westinghouse EM:
19230F Virgil C.SummerUnit1 Large break
- WestinghouseEM Blowdown:
1814F Reflood 1:
18140F Reflood 2:
1961F Composite:
19610F TheLOCAresults forMPS2and3,NAPS 1and 2,SPS1and2,andVCS1areconfirmed tohavesufficient margin tothe2200Flimit for PCTspecifiedin10CFR50.46.
Based ontheevaluation ofthis information andtheresulting changes intheapplicable licensing basis PCTresults, nofurther action isrequired to demonstrate compliance withthe10 CFR50.46 requirements.
Theinformation contained herein satisfies the2020annual reporting requirements of10 CFR50.46(a)(3)(ii).
Ifyouhaveanyquestions regarding this submittal, please contact Ms. CathieTiernan at (804) 432-2596.
Respectfully, w
/
MarkD.Sartain VicePresident
- Nuclear Engineering andFleet Support Dominion Energy Nuclear Connecticut, Inc.
Dominion Energy South
- Carolina, Inc Virginia Electric andPowerCompany Commitments madeinthis letter:
None I
Serial No.21-183 Docket Nos.50-336/423/338/339/280/281/3 2020Annual 10CFR50.46 Report Page3of4 Attachments:, Report ofChanges inFramatome andWestinghouse ECCSEvaluation Models Attachment 2.2020 Annual Reporting of10CFR50.46 Margin Utilization
- Millstone PowerStation Units2and3 Attachment 3.2020Annual Reporting of10CFR50.46 Margin Utilization
- North Anna Power StationUnits 1and2 Attachment 4.2020Annual Reporting of10CFR50.46 Margin Utilization
- Surry Power Station Units 1and2 Attachment 5.2020Annual Reporting of10CFR 50.46 Margin Utilization
- Virgil C.
SummerNuclear Station cc: U.S.Nuclear Regulatory Commission, Region I
Regional Administrator 2100Renaissance Blvd.,
Suite 100 KingofPrussia, PA 19406-2713 U.S.Nuclear Regulatory Commission, Region II Regional Administrator Marquis OneTower 245Peachtree Center Ave.,NESuite 1200
- Atlanta, Georgia 30303-1257 NRCSenior Resident Inspector Millstone PowerStation NRCSenior Resident Inspector North AnnaPowerStation NRCSenior Resident Inspector Surry PowerStation NRCSenior Resident Inspector Virgil C.SummerPowerStation Mr.G.Edward Miller NRCProject Manager
- North Anna U.S.Nuclear Regulatory Commission OneWhiteFlint North MailStop09E3 11555Rockville Pike Rockville, MD20852-2738
Serial No.21-183 Docket Nos.50-336/423/338/339/280/281/
2020Annual 10CFR50.46 Report Page4of4 Mr. R.Guzman NRC Project Manager
- Millstone Units 2and3 U.S. Nuclear Regulatory Commission OneWhite Flint North Mail Stop O8 C2 11555 Rockville Pike Rockville, MD 20852-2738 Mr.Vaughn Thomas NRCProject Manager Surry andVirgil C.Summer U.S.Nuclear RegulatoryCommission OneWhite Flint North Mail Stop04F12 11555Rockville Pike Rockville, MD20852-2738 Mr.Marcus Harris OldDominion Electric Cooperative Innsbrook Corporate
- Center, Suite 300 4201Dominion Blvd.
GlenAllen, Virginia 23060
Attachment 1
2020ANNUALREPORTOFEMERGENCY CORE PURSUANT TOTHEREQUIREMENTS OF 10CFR50.46 REPORTOFCHANGESIN FRAMATOME ANDWESTINGHOUSE ECCSEVALUATION MODELS DOMINIONENERGYNUCLEARCONNECTICUT, INC.
VIRGINIA ELECTRICANDPOWERCOMPANY DOMINIONENERGYSOUTHCAROLINA,INC.
MILLSTONEPOWERSTATIONUNITS2AND3 NORTHANNAPOWERSTATIONUNITS 1AND2 SURRYPOWERSTATIONUNITS1AND2 VIRGIL C.SUMMERNUCLEARSTATIONUNIT1
Serial Number21-183 Docket Nos.50-336/423/338/339/280/281 Attachment 1
Page2of5 REPORTOFCHANGESIN FRAMATOME ANDWESTINGHOUSEECCSEVALUATION MODELS Millstone Power Station Unit2 1
Framatome identified nochangesorerrors applicable totheEMF-2328(P)(A),
Revision 0
with Supplement 1 evaluation modelforSmall Break LossofCoolant Accident (SBLOCA) forMillstone Unit 2during 2020.
2.
Framatome identified nochanges orerrors applicable totheSEM/PWR-98 evaluation modelforLarge Break LOCA (LBLOCA) forMillstone Unit 2during 2020.
This evaluation model isapplicable tothe Millstone Unit2fuel with zr-4 cladding.
3.
OnJanuary 24,2017,anewLBLOCA analysis wasapproved bytheNRC,Reference 8,
basedupontheEMF-2103(P)(A),
Revision 3,"Realistic Large Break LOCA(RLBLOCA)
Methodology forPressurized Water Reactors" Thenewanalysis isapplicable tothe AREVAStandard CE14HTPfuel product with the M5TMfuel rodcladding only.
The analysis predicted aPCTof1615F.
Framatome identified thefollowing change anderrorapplicable totheEMF-2103(P)(A),
Revision 3evaluation model forRLBLOCAfor Millstone Unit 2during2020.
- M Aninconsistency wasidentified inS-RELAP5 inputs related tofuel rodradiation enclosures.
Theerror occurs onlyinapplications ofthe Framatome EMF-2103(P)(A),
Revision 3,Realistic Large Break LOCA(RLBLOCA) methodology.Fuel stored energy uncertainty established forsimulation oflimiting fuel rodswasinadvertently applied to thehotfresh andonce-burned UO2rodradiation enclosures.
Theintentof the methodology isthat theuncertainty forenclosure stored energy simulation matches that ofthehotfuel
- assembly, which hasnoapplied uncertainty.
Enclosures account fortheeffect ofrod-to-rod thermal radiation.
Rod-to-rod radiation comprises afraction ofthetotal heattransfer characteristic offuel rodsinasteam environment.
Theeffect oftheinput error issmall since thetotal heattransfer froman uncovered fuel rodisrelatively small.
Theimposition ofstored energy uncertainty can causeradiation heat transfer fromalimiting rodtosurrounding rodstoeither increase or decrease asaresult oftheerror.
Corrections havebeenmadetotheinput sothat uncertainty adjustments arenotmade tothehotfresh andonce-burned UO2rodradiation enclosures.
Before andafter runs ofCombustion Engineering (CE) sample casesetsweresubsequently compared.
Differences intheresults arenegligible.
Thus,there isnoeffect ontheRevision 3
RLBLOCAanalyses ofrecord peakcladtemperature calculations.
Effects oftheinput error onmaximumlocal andwhole coreoxidation calculations arenegligible aswell.
Serial Number21-183 Docket Nos.50-336/423/338/339/280/281 Attachment 1
Page3of5 Millstone Power StationUnit3 1
Westinghouse identified thefollowing changes applicable tothe1985Westinghouse SBLOCAEvaluation Model withNOTRUMP forMillstone Unit 3during 2020.
TheWestinghousePerformance Analysis andDesign Model(PAD) isusedtogenerate fuel performance input data foruseinSBLOCAanalyses.
A newapproved PADmodel (PAD5, WCAP-17642-P-A, Revision 1)isnowavailable forgeneration offuel performance input data.
PAD5 implementation hasbeenevaluated through theuseof qualitative examination andsensitivity calculations tohaveanegligible effect onthe SBLOCAanalysis
- results, leading to anestimated peakcladding temperature impact of 0F.
2.
Westinghouse identified thefollowing change applicable tothe2004Westinghouse Best Estimate (BE)
LBLOCAEvaluation Model(EM) using theAutomated Statistical Treatment ofUncertainty Method (ASTRUM) for Millstone Unit 3during 2020:
TheMillstone Unit 3Cycle 21reload coredesign resulted inviolations ofthe PBOT/PMID envelope usedintheLBLOCA analysis.
These violations wereevaluated forMillstone Unit 3Cycle 21operation.
Thepeakcladdingtemperature impact ofthe PBOT/PMID violations forMillstone Unit 3Cycle 21wasdetermined viaaplant-specific evaluation tobe0F.
North AnnaPowerStation Units 1and2 1.
Westinghouse identified nochanges orerrors applicable tothe1985 Westinghouse SBLOCAEvaluation ModelwithNOTRUMP forNorth AnnaUnits 1and2during 2020.
2.
Westinghouse identified nochanges orerrors applicable tothe2004WestinghouseBE LBLOCAEMusing ASTRUMforNorth AnnaUnits 1and2during 2020.
M 1.
Westinghouse identified nochanges orerrors applicable tothe1985Westinghouse SBLOCAEvaluation Modelwith NOTRUMP forSurry Units 1and2during 2020.
2.
Westinghouse identified nochanges orerrors applicable tothe2004Westinghouse BE LBLOCAEMusing ASTRUMforSurry Units 1and2during 2020.
Serial Number 21-183 Docket Nos.50-336/423/338/339/280/281/
Attachment 1
Page4of5 Virgil CSurnmer 1.
Westinghouse identified thefollowing change applicable tothe1985Westinghouse SBLOCAEvaluation Model withNOTRUMPforVirgil C.Summerduring 2020.
Evaluationof an increased Vessel Average Temperature Uncertainty Anupdate tothe analysis ofrecord(AOR) forsetpoint andcontrol uncertainties resulted inanincrease tothevessel average temperature(Tavg) uncertainty range for consideration intheLOCA analyses.
Theuncertainty rangechanged from+5.40F
/
6.3Fto+6.4F/-6.30F.
The change intemperatureuncertainty hasbeenevaluated fortheSBLOCAanalysis basis.
This change represents aChangeinPlant Configuration orSetpoints, distinguished fromanevaluation modelchangeinSection 4
ofWCAP-3451.
Theevaluation determined that the increased Tavg uncertainty will haveanegligible effect ontheSBLOCAtransient
- results, leading toanestimatedpeakcladding temperature impact of0F.
2.
Westinghouse identified thefollowing change applicable tothe1996Westinghouse Best Estimate LBLOCAEvaluation ModelforVirgil C.Summer during 2020.
- Evaluation ofanIncreased Vessel Average Temperature Uncertainty Anupdate totheAORforsetpoint andcontrol uncertainties resulted inanincrease to thevessel average temperature (Tavg) uncertainty range for consideration intheLOCA analyses.
Theuncertainty range changed from+5.4F/-6.3Fto+6.4F
/-6.30F.The change intemperature uncertainty hasbeenevaluated forthebest-estimate LBLOCA andFULLSPECTRUM LOCA(FSLOCA)
Evaluation Model(EM) analyses.
This change represents aChangeinPlant Configuration orSetpoints, distinguished from an evaluation modelchange inSection 4ofWCAP-13451.
A qualitative evaluation basedonthemodeled Tavgdetermined that theincreased uncertainty range will haveanegligible effect ontheanalysis results forthebest-estimate LBLOCAandFSLOCAEManalyses, leading toanestimated PCTimpact of 0F.
Conclusion TheLOCAresults forMillstone Units 2and3,North AnnaUnits 1and2,Surry Units 1and2and Virgil C.SummerUnit1areconfirmed inthePCTrackup
- tables, Attachments 2through 5,to havemargin tothe22000F limit forPCTspecified in10CFR50.46.
Basedontheevaluation of this information andtheresulting changes intheapplicable licensing basis PCTresults, no further action isrequired todemonstrate compliance withthe10CFR50.46requirements.
Reporting ofthisinformation isrequired per10CFR50.46(a)(3)(ii),
whichobligates each
Serial Number21-183 Docket Nos.50-336/423/338/339/280/281/
Attachment 1
Page5of5 licenseeto report theeffect uponcalculated temperature ofanychange orerror inevaluation models ortheir application onanannual basis.
Thisinformation satisfies theannual reporting requirements of10CFR50.46(a)(3)(ii for calendar year 2020.
Attachment 2
2020ANNUALREPORTOFEMERGENCY CORE PURSUANT TOTHEREQUIREMENTSOF 10CFR50.46 2020ANNUALREPORTING OF10CFR50.46 MARGIN UTILizATION DOMINION ENERGYNUCLEARCONNECTICUT, INC.
MILLSTONE POWERSTATIONUNITS2AND3
Serial Number 21-183 Docket Nos.50-336/423 Attachment 2
Page2of8 10CFR 50.46 MARGIN UTILIzATION
- SMALLBREAKLOCA Plant Name:
Millstone PowerStation, Unit 2
Utility Name:
DominionEnergy Nuclear Connecticut, Inc.
Ajialy.sis I.ggLormatLn EM: 2015, Supp. 1,SBLOCA, S-RELAP5 Based Limiting BreakSize:3.78 Inches Analysis Date:
April 2015 Vendor:
Framatome PeakLinear Power:
15.1 kW/ft Notes:
None ClfidTe!np.f.D LICENSINGBASIS Analysis ofRecord PCT 1707 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
zirc-4 Product Penalty 4
2.
M5LOCASwelling andRupture 0
3.
S-RELAP5 Oxidation Calculations 3
B.
Planned PlantModification Evaluations 1.
None 0
C.
2020ECCSModelAssessments 1
None 0
D.
Other 1
None 0
LICENSINGBASISPCT+PCTASSESSMENTS PCT=
1714
Serial Number21-183 Docket Nos.50-336/423 Attachment 2
Page3of8 10CFR50.46 MARGINUTILIzATION
- LARGEBREAKLOCA Plant Name:
Millstone PowerStation, Unit 2
Utility Name:
DominionEnergy Nuclear Connecticut, Inc.
Agly.sis In[ogm.gitig EM:
SEM/PWR-98 Limiting BreakSize:
1.0DECLG Analysis Date:
November 1998 Vendor:
Framatome PeakLinear Power:
15.1 kW/ft Notes:
None C-.liLdT.egItp.[?Fj LICENSINGBASIS Analysis ofRecord PCT 1814 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
Corrected Corrosion Enhancement Factor
-1 2.
ICECONCoding Errors 0
3.
Setting RFPACFuel Temperatures atStart ofReflood
-2 4.
SISPUNCH/ujun98 CodeError 0
5.
Error inFlowBlockage ModelinTOODEE2 0
6.
Change inTOODEE2-Calculation ofQMAX 0
7.
Change inGadolinia Modeling 0
8.
PWRLBLOCASplit Break Modeling 0
9.
TEOBYCalculation Error 0
- 10. Inappropriate HeatTransfer inTOODEE2 0
11 End-of-Bypass Prediction byTEOBY 0
- 12. R4SSOverwrite ofJunction Inertia 0
- 13. Incorrect Junction Inertia Multipliers 1
- 14. Errors Discovered During RODEX2V&V 0
- 15. Error inBroken LoopSGTubeExit Junction Inertia 0
- 16. RFPACRefill andReflood Calculation CodeErrors 16
- 17. Incorrect PumpJunction AreaUsedinRELAP4 0
- 18. Error inTOODEE2CladThermal Expansion
-1
- 19. Accumulator LineLossError
-1
- 20. Inconsistent LossCoefficients UsedforRobinson LBLOCA 0
- 21. PumpHeadAdjustment forPressure Balance Initialization
-3
- 22. ICECONCodeErrors 0
- 23. Containment SumpModification andReplacement P2R 2
- 24. Non-Conservative RODEXFuel Pellet Temperature 20
- 25. Array Index Issues intheRELAP4Code 0
B.
Planned Plant Modification Evaluations 1.
None 0
C.
2020ECCSModelAssessments 1.
None 0
Serial Number21-183 Docket Nos.50-336/423 Attachment 2
Page4of8 D.
Other 1
None 0
LICENSINGBASIS PCT+PCTASSESSMENTS PCT=
1845
Serial Number 21-183 Docket Nos.50-336/423 Attachment 2
Page5of8 10CFR50.46 MARGINUTILIzATION
- LARGEBREAKLOCA Plant Name:
Millstone PowerStation, Unit 2(M5Fuel)
Utility Name:
DominionEnergy Nuclear Connecticut, Inc.
An.ajysis JJ1form.atta.
EM:
EMF-2103 Limiting Break Size:
1.0DEGB Analysis Date:
May 2016 Vendor:
Framatome PeakLinear Power:
15.1 kW/ft Notes:
None h
LICENSINGBASIS Analysis ofRecord PCT 1615 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
Placement ofHotLegPiping Form Loss Coefficient 0
2.
M5LOCASwelling andRupture 0
3.
S-RELAP5 Oxidation Calculations 0
4.
Cathcart-Pawel correlation implementation 0
5.
Rodpressure notreset after rupture inS-RELAPS LOCAcalculations B.
Planned Plant Modification Evaluations 1
None 0
C.
2020ECCSModelAssessment 1.
Radiation enclosure input error 0
D.
Other 1
None 0
LICENSINGBASISPCT+PCTASSESSMENTS PCT=
1615
Serial Number 21-183 Docket Nos.50-336/423 Attachment 2
Page6of8 10CFR 50.46 MARGIN UTILIzATION
- SMALLBREAKLOCA Plant Name:
Millstone PowerStation, Unit3 Utility Name:
DominionEnergy Nuclear Connecticut, Inc.
A.nalygisjkrmatta EM:
NOTRUMP Limiting BreakSize:4inches Analysis Date:
02/07/07 Vendor:
Westinghouse FQ:
2.6 FdH:
1.65 Fuel:
RFA-2 SGTP(%): 10 Notes:
None
.C[ajLTempCF)
LICENSING BASIS Analysis ofRecord PCT 1193 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1
Errors inReactor Vessel Lower Plenum Surface Area Calculations 0
2.
Discrepancy inMetal Masses UsedFromDrawings 0
3.
Urania-Gadolinia Pellet Thermal Conductivity Calculation 0
4.
Pellet Crack andDishVolume Calculation 0
5.
Treatment ofVessel Average Temperature Uncertainty 0
6.
MaximumFuel RodTimeStep Logic 0
7.
Radiation HeatTransfer Logic 0
8.
NOTRUMP-EM Evaluation ofFuelPellet Thermal 0
Conductivity Degradation 9.
SBLOCTACladding Strain Requirement forFuel 0
RodBurst
- 10. Fuel RodGapConductance Error 0
- 11. Radiation HeatTransfer Model Error 0
- 12. SBLOCTAPre-DNBCladding HeatTransfer 0
Coefficient Calculation
- 13. Insertion ofAXIOM'rM Cladding LTAs 0
- 14. Vessel Average Temperature Uncertainty 0
- 15. Error intheUpperPlenum Fluid Volume Calculation g
- 16. UO2Fuel Pellet HeatCapacity 0
B.
Planned Plant Modification Evaluations 1
None C.
2020ECCSModelAssessments 1
Small Break LOCAPAD5Implementation 0
D.
Other l
None 0
LICENSINGBASISPCT+PCTASSESSMENTS PCT=
1193
Serial Number21-183 Docket Nos.50-336/423 Attachment 2
Page7of8 10CFR50.46 MARGINUTILIzATION
- LARGEBREAKLOCA Plant Name:
Millstone PowerStation, Unit 3
Utility Name:
DominionEnergy Nuclear Connecticut, Inc.
Ana.lysisinfoLma.tion EM:
ASTRUM (2004) Limiting BreakSize:Guillotine Analysis Date:
04/17/07 Vendor:
Westinghouse FQ:
2.6 FdH:
1.65 Fuel:
RFA-2 SGTP(%):
10 Notes:
None Ch LICENSINGBASIS Analysis ofRecord PCT 1781 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
HOTSPOT Burst Temperature LogicErrors 0
2.
CCFLGlobal VolumeError 0
3.
HOTSPOTGapHeatTransfer Logic 0
4.
Discrepancy inMetal Masses UsedFromDrawings 0
5.
Error inASTRUMProcessing ofAverage RodBurnup andRodInternal Pressure 0
6.
Treatment ofVessel Average Temperature Uncertainty 0
7.
PBOTandPMIDEvaluation 0
8 Evaluation ofFuelPellet Thermal Conductivity 222 Degradation 9.
HOTSPOT Burst Temperature Calculation 0
forzIRLOCladding
- 10. RodInternal Pressure Calculation 0
- 11. HOTSPOTIteration Algorithm forCalculating the 0
Initial Fuel Pellet Average Temperature
- 12. WCOBRA/TRAC Thermal-Hydraulic History File 0
Dimension usedinHSDRIVERBackground
- 13. WCOBRA/TRAC Automated Restart Process Logic Error 0
- 14. Initial Fuel Pellet Average Temperature Uncertainty 0
Calculation
- 15. Elevations forHeatSlab Temperature Initialization0
- 16. HeatTransfer Model Error Corrections 0
- 17. Correction toHeatTransfer NodeInitialization 0
- 18. MassConservation Error Fix 0
19 Correction toSplit Channel MomentumEquation 0
- 20. HeatTransfer Logic Correction forRodBurst Calculation0
- 21. Changes toVessel Superheated SteamProperties 0
- 22. Update toMetal Density Reference Temperatures 0
- 23. DecayHeatModelError Corrections 0
- 24. Correction tothePipe Exit Pressure DropError 0
- 25. WCOBRA/TRAC Ul9File Dimension Error Correction0
Serial Number21-183 Docket Nos.50-336/423 Attachment 2
Page8of8 26.
RevisedHeatTransfer Multiplier Distributions
-91 27.
HOTSPOT BurstStrain Error Correction 21 28.
Changes toGridBlockage Ratio andPorosity 0
29.
Grid HeatTransferEnhancement Calculation 0
30.
Burst Elevation Selection 0
31.
Errors in Decay Group Uncertainty Factors 0
- 32. Errorsin Support Plate, CoreBarrel, andVessel Wall 0
UnheatedConductor
- 33. Error inOxidation Calculations 0
- 34. Error inuseofASME SteamTables 0
- 35. Insertion ofAXIOMTM Cladding LTAs 0
- 36. Vessel Average Temperature Uncertainty 0
- 37. Inconsistent Applicationof Numerical RampApplied 0
totheEntrained Liquid
/Vapor Interfacial DragCoefficient
- 38. Inappropriate Resetting ofTransverse LiquidMassFlow 0
- 39. Steady-State Fuel Temperature Calibration Method 0
40.
Millstone Unit3Cycle 20PBOT/PMID Violations 0
41 Vapor Temperature Resetting 0
42 CoreBarrel HeatSlab Error 0
- 43. ColdLegVolume Error 0
44.
CoreBarrel Wetted Perimeter Error 0
- 45. Removal oftheVessel Interfacial HeatTransfer Limit 0
B.
Planned Plant Modification Evaluations 1
None C.
2020ECCSModelAssessments 1.
Cycle 21PBOT/PMID Envelope Violations 0
D.
Other 1.
None 0
LICENSINGBASISPCT+PCTASSESSMENTS PCT=
1933
Attachment 3
2020ANNUALREPORTOFEMERGENCY CORE PURSUANT TOTHEREQUIREMENTS OF 10CFR50.46 2020ANNUALREPORTING OF10CFR50.46 MARGINUTILIzATION VIRGINIA ELECTRICANDPOWERCOMPANY NORTHANNAPOWERSTATIONUNITS1AND2
Serial Number21-183 Docket Nos.50-338/339 Attachment 3
Page2of7 10CFR 50.46 MARGIN UTILI2ATION
- WESTINGHOUSE SMALLBREAKLOCA Plant Name:
North AnnaPowerStation, Unit1 Utility Name:
VirginiaElectric andPowerCompany Agga.lyjs Inform.atiog1 EM:
NOTRUMP Limiting BreakSize:2.75inches Analysis Date:
12/20/2010 Vendor:
Westinghouse FQ:
2.32 FAH:
1.65 Fuel:
RFA-2 SGTP(%): 7 Notes:
None h
LICENSINGBASIS Analysis ofRecord PCT 1834.1 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
NOTRUMP-EM Evaluation ofFuel Pellet Thermal 0
Conductivity Degradation 2.
SBLOCACladding Strain Requirement for Fuel 0
RodBurst 3.
Fuel RodGapConductance Error 0
4.
Radiation HeatTransfer ModelError 0
5.
SBLOCTAPre-DNBCladding HeatTransfer 0
Coefficient Calculation 6.
Error intheUpper Plenum Fluid VolumeCalculation 0
7.
UO2FuelPellet HeatCapacity 0
B.
Planned Plant Modification Evaluations 1
None 0
C.
2020ECCSModelAssessments 1
None 0
D.
Other 1.
None 0
LICENSINGBASISPCT+PCTASSESSMENTS PCT=
1834.1
Serial Number21-183 Docket Nos.50-338/339 Attachment 3
Page3of7 10CFR 50.46 MARGIN UTILIzATION
- WESTINGHOUSE LARGEBREAKLOCA Plant Name:
North AnnaPowerStation, Unit1 Utility Name:
VirginiaElectric andPowerCompany Ah EM:
ASTRUM (2004) Limiting BreakSize:DEGB Analysis Date:
8/25/2010 Vendor:
Westinghouse FQ:
2.32 FAH:
1.65 Fuel:
RFA-2 SGTP(%): 7 Notes:
CorePower5 100%of2951MWt; SG Model 54F;17xl7 RFA-2Fuel with zIRLO@orOptirnized zIRLOTM
- cladding, Non-IFBA orIFBA,IFMs CladT.e!!!p.LCFj LICENSINGBASIS Analysis ofRecord PCT 1852 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1
Evaluation ofFuel Pellet Thermal Conductivity 135 Degradation 2.
HOTSPOTBurst Temperature Calculation 0
forzIRLOCladding 3.
RodInternal Pressure Calculation 0
4.
HOTSPOTIteration Algorithm.
forCalculating the 0
Initial Fuel Pellet Average Temperature 5.
WCOBRA/TRAC Thermal-Hydraulic History File 0
Dimension usedinHSDRIVERBackground 6.
WCOBRA/TRAC Automated Restart Process Logic Error 0
7.
Initial FuelPellet Average Temperature Uncertainty 1
Calculation 8.
Elevations forHeatSlabTemperature Initialization0 9.
HeatTransfer Model Error Corrections 0
- 10. Correction toHeatTransfer NodeInitialization 0
11 MassConservation Error Fix 0
- 12. Correction toSplit Channel MomentumEquation 0
- 13. HeatTransfer Logic Correction forRodBurst Calculation 0
- 14. Changes toVessel Superheated SteamProperties 0
- 15. Update toMetal Density Reference Temperatures 0
- 16. Decay HeatModel Error Corrections 0
- 17. Correction tothePipeExit Pressure DropError 0
- 18. WCOBRA/TRAC Ul9File Dimension Error Correction 0
- 19. Revised HeatTransfer Multiplier Distributions
-27
- 20. HOTSPOTBurst Strain Error Correction 21
- 21. Changes toGridBlockage Ratio andPorosity 0
- 22. GridHeatTransfer Enhancement Calculation 0
Serial Number 21-183 Docket Nos.50-338/339 Attachment 3
Page4of7 23.
VesselSection 7Mid-Level Elevation Modeling 0
24.
Burst ElevationSelection 0
25.
Errors inDecay Group Uncertainty Factors 0
26.
Error inOxidation Calculations 0
27.
Error inuseofASMESteam Tables 0
28.
Support Column CoreBarrel Unheated Conductor Errors0 0
29.
Inconsistent Application ofNumerical RampApplied 0
tothe Entrained Liquid /Vapor Interfacial DragCoefficient 30.
InappropriateResetting ofTransverseLiquid MassFlow 0
- 31. Steady-State Fuel Temperature CalibrationMethod 0
- 32. Correction toFuel Pellet TCD Assessment 0
- 33. Vapor Temperature Resetting 0
- 34. Removal oftheVessel Interfacial HeatTransferLimit 0
B.
Planned Plant Modification Evaluations 1.
None 0
C.
2020ECCSModelAssessments 1.
None 0
D.
Other 1.
None LICENSINGBASISPCT+PCTASSESSMENTS PCT=
1982
Serial Number 21-183 Docket Nos.50-338/339 Attachment 3
Page5of7 10CFR 50.46 MARGIN UTILIzATION
- WESTINGHOUSE SMALLBREAKLOCA Plant Name:
NotthAnnaPowerStation, Unit 2
Utility Name:
VirginiaElectric andPowerCompany An.a.lysisJnforg!1ation EM:
NOTRUMP Limiting BreakSize:2.75inches Analysis Date:
12/20/2010 Vendor:
Westinghouse FQ:
2.32 FAH:
1.65 Fuel:
RFA-2 SGTP(%): 7 Notes:
None M
LICENSING BASIS Analysis ofRecord PCT 1834.1 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
NOTRUMP-EMEvaluation ofFuel Pellet Thermal 0
Conductivity Degradation 2.
SBLOCTACladding Strain Requirement forFuel 0
RodBurst 3.
Fuel RodGapConductance Error 0
4.
Radiation HeatTransfer Model Error 0
5.
SBLOCTAPre-DNB Cladding HeatTransfer 0
Coefficient Calculation 6.
Error intheUpperPlenum Fluid Volume Calculation 0
7.
UO2Fuel Pellet HeatCapacity 0
B.
Planned Plant Modification Evaluations l
None 0
C.
2020ECCSModelAssessments 1.
None 0
D.
Other 1.
None 0
LICENSING BASISPCT+PCTASSESSMENTS PCT=
1834.1
Serial Number21-183 Docket Nos.50-338/339 Attachment 3
Page6of7 10CFR 50.46 MARGIN UTILIzATION
- WESTINGHOUSE LARGEBREAKLOCA Plant Name:
North AnnaPowerStation, Unit 2
Utility Name:
Virginia Electric andPowerCompany Ah EM:
ASTRUM (2004)
Limiting BreakSize:DEGB Analysis Date:
8/25/2010 Vendor:
Westinghouse FQ:
2.32 FAH:
1.65 Fuel:
RFA-2 SGTP(%): 7 Notes:
CorePower 5 100%of2951MWt;SG Model 54F;17xl7 RFA-2Fuel with zIRLO@orOptimized 2IRLOTM
- cladding, Non-IFBA orIFBA,IFMs M
LICENSINGBASIS Analysis ofRecord PCT 1852 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
Evaluation ofFuelPellet Thermal Conductivity 135 Degradation 2.
HOTSPOTBurst Temperature Calculation 0
forzIRLOCladding 3.
RodInternal Pressure Calculation 0
4.
HOTSPOT Iteration Algorithm forCalculating the 0
Initial Fuel Pellet Average Temperature 5.
WCOBRA/TRAC Thermal-Hydraulic History File 0
Dimension usedinHSDRIVERBackground 6.
WCOBRA/TRAC Automated Restart Process Logic Error 0
7.
Initial Fuel Pellet Average Temperature Uncertainty I
Calculation 8
Elevations forHeatSlab Temperature Initialization0 9.
HeatTransfer Model Error Corrections 0
- 10. Correction toHeatTransfer NodeInitialization 0
l1.
MassConservation Error Fix 0
- 12. Correction toSplit Channel MomentumEquation 0
- 13. HeatTransfer Logic Correction forRodBurst Calculation0
- 14. Changes toVessel Superheated SteamProperties 0
- 15. Update toMetal Density Reference Temperatures 0
- 16. DecayHeatModelError Corrections 0
- 17. Correction tothePipe Exit Pressure DropError 0
- 18. WCOBRA/TRAC Ul9File Dimension Error Correction 0
- 19. Revised HeatTransfer Multiplier Distributions
-27
- 20. HOTSPOTBurst Strain Error Correction 21
- 21. Changes toGridBlockage Ratio andPorosity 0
Serial Number 21-183 Docket Nos.50-338/339 Attachment 3
Page7of7 22.
Grid HeatTransfer Enhancement Calculation 0
23.
Vessel Section 7Mid-Level Elevation Modeling 0
24.
Burst Elevation Selection 0
25.
Errors inDecayGroupUncertainty Factors 0
27.
Error in Oxidation Calculations 0
28.
Errorin use ofASMESteamTables 0
29.
SupportColumn CoreBarrel Unheated Conductor Errors 0
30.
InconsistentApplication ofNumerical RampApplied 0
tothe Entrained Liquid /Vapor Interfacial DragCoefficient 31 Inappropriate Resetting ofTransverse Liquid MassFlow 0
- 32. Steady-State Fuel Temperature Calibration Method 0
- 33. Correction toFuel Pellet TCD Assessment 0
- 34. VaporTemperature Resetting 0
35.
Removal oftheVessel Interfacial Heat Transfer Limit 0
B.
Planned Plant Modification Evaluations 1
None 0
C.
2020ECCSModelAssessments 1.
None 0
D.
Other 1,
None LICENSINGBASISPCT+PCTASSESSMENTS PCT=
1982
Attachment 4
2020ANNUALREPORTOFEMERGENCY CORE 2020ANNUALREPORTING OF10CFR50.46 MARGINUTILIzATION VIRGINIA ELECTRICANDPOWERCOMPANY SURRYPOWERSTATIONUNITS1AND2
Serial Number21-183 Docket Nos.50-280/281 Attachment 4
Page2of7 10CFR 50.46 MARGIN UTILIzATION
- WESTINGHOUSE SMALLBREAKLOCA Plant Name:
Surry PowerStation, Unit1 Utility Name:
VirginiaElectric andPowerCompany An.alyjsln&rma.1ion EM:
NOTRUMP Limiting BreakSize:2.75inches Analysis Date:
5/7/2009 Vendor:
Westinghouse FQ:
2.5 FAH:
1.7 Fuel:
Upgrade SGTP(%):
7 Notes:
None M
LICENSINGBASIS Analysis ofRecord PCT 2012 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
Urania-Gadolinia Pellet Thermal Conductivity Calculation.
0 2.
Pellet Crack andDishVolume Calculation.
0 3.
Treatment ofVessel Average Temperature Uncertainty 0
4.
15X15Upgrade Fuel 0
5.
MaximumFuel RodTimeStepLogic 0
6.
Radiation HeatTransfer Logic 0
7.
NOTRUMP-EM Evaluation ofFuel Pellet Thermal 0
Conductivity Degradation 8.
SBLOCTACladding Strain Requirement forFuel 0
RodBurst 9.
Fuel RodGapConductance Error 0
- 10. Radiation HeatTransfer Model Error 0
- 11. SBLOCTAPre-DNBCladding HeatTransfer 0
Coefficient Calculation
- 12. Error intheUpper Plenum Fluid Volume Calculation 0
- 13. UO2FuelPellet HeatCapacity 0
B.
Planned Plant Modification Evaluations 1.
None 0
C.
2020ECCSModelAssessments 1.
None 0
D.
Other 1.
None 0
LICENSINGBASISPCT+PCTASSESSMENTS PCT=
2012
Serial Number21-183 Docket Nos.50-280/281 Attachment 4
Page3of7 10CFR 50.46 MARGIN UTILIzATION-WESTINGHOUSE LARGEBREAKLOCA Plant Name:
Surry PowerStation, Unit 1
Utility Name:
VirginiaElectric andPowerCompany Analy.sisln[oLmation EM:
ASTRUM (2004) Limiting BreakSize:DEG Analysis Date:
10/6/2010 Vendor:
Westinghouse FQ:
2.5 FAH:
1.7 Fuel:
Upgrade SGTP(%): 7 Notes:
None ClagLT.emILCF)
LICENSINGBASIS Analysis ofRecord PCT 1853 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
Evaluation ofFuel Pellet Thermal Conductivity 183 Degradation 2.
Pellet Radial Profile Option
-13 3.
HOTSPOT Burst Temperature Calculation 0
forzIRLOCladding 4.
RodInternal Pressure Calculation 0
5.
HOTSPOTIteration Algorithm forCalculating the 0
Initial Fuel Pellet Average Temperature 6.
WCOBRA/TRAC Thermal-Hydraulic History File 0
Dimension used inHSDRIVERBackground 7.
WCOBRA/TRAC Automated Restart Process Logic Error 0
8.
Initial Fuel Pellet Average Temperature Uncertainty 0
Calculation 9.
Elevations forHeatSlab Temperature Initialization0
- 10. HeatTransfer Model Error Corrections 0
11 Correction toHeatTransfer NodeInitialization 0
- 12. MassConservation Error Fix 0
- 13. Correction toSplit Channel MomentumEquation 0
- 14. HeatTransfer Logic Correction forRodBurst Calculation0
- 15. Changes toVessel S.uperheated SteamProperties 0
- 16. Update toMetal Density Reference Temperatures 0
- 17. Decay HeatModel Error Corrections 0
- 18. Correction tothePipe Exit Pressure DropError 0
- 19. WCOBRA/TRAC Ul9File Dimension Error Correction 0
- 20. Revised HeatTransfer Multiplier Distributions
-7 21 HOTSPOTBurst Strain Error Correction 51
- 22. Changes toGridBlockage Ratio andPorosity 0
- 23. Grid HeatTransfer Enhancement Calculation 0
- 24. Vessel Section 7Mid-Level Elevation Modeling 0
Serial Number 21-183 Docket Nos.50-280/281 Attachment 4
Page4of7 25.
BurstElevation Selection 0
26.
Errors inDecayGt;oup Uncertainty Factors 4
27.
Evaluation ofAdditional Containment Metal 0
28.
Error inOxidation Calculations 0
29.
Error inuseofASMESteamTables 0
- 30. CoreBarrel Unheated Conductor Errors 0
31.
Discrepancy inWetted Perimeter Inputs 0
32.
InconsistentApplication ofNumerical RampApplied 0
tothe Entrained Liquid /Vapor Interfacial DragCoefficient
- 33. Inappropriate Resetting ofTransverse Liquid MassFlow 0
- 34. Steady-State Fuel Temperature Calibration Method 0
- 35. VaporTemperature Resetting 0
- 36. Removal oftheVessel Interfacial HeatTransfer Limit 0
B.
Planned Plant Modification Evaluations 1.
None 0
C.
2020ECCSModelAssessments 1,
Removal oftheVessel Interfacial Heat Transfer Limit 0
D.
Other 1.
None 0
LICENSINGBASISPCT+PCTASSESSMENTS PCT=
2071
Serial Number21-183 Docket Nos.50-280/281 Attachment 4
Page5of7 10CFR 50.46 MARGIN UTILI2ATION
- WESTINGHOUSE SMALLBREAKLOCA Plant Name:
Surry PowerStation, Unit 2
Utility Name:
VirginiaElectric andPowerCompany hEM:
NOTRUMP Limiting BreakSize:2.75 inches Analysis Date:
5/7/2009 Vendor:
Westinghouse FQ:
2.5 FAH:
1.7 Fuel:
Upgrade SGTP(%): 7 Notes:
None Clad.Temp fF.)
LICENSINGBASIS Analysis ofRecord PCT 2012 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
Urania-Gadolinia Pellet Thermal Conductivity Calculation.
0 2.
Pellet Crack andDishVolume Calculation.
0 3.
Treatment ofVessel Average Temperature Uncertainty 0
4.
15X15Upgrade Fuel 0
5.
MaximumFuel RodTimeStepLogic 0
6.
Radiation HeatTransfer Logic 0
7.
NOTRUMP-EM Evaluation ofFuelPellet Thermal 0
Conductivity Degradation 8.
SBLOCTACladding Strain Requirement forFuel 0
RodBurst 9.
FuelRodGapConductance Error 0
- 10. Radiation HeatTransfer Model Error 0
11 SBLOCTAPre-DNB Cladding HeatTransfer 0
Coefficient Calculation
- 12. Error intheUpper Plenum Fluid VolumeCalculation 0
- 13. UO2FuelPellet HeatCapacity 0
B.
Planned PlantModification Evaluations 1.
None 0
C.
2020ECCSModelAssessments 1.
None 0
D.
Other 1
None 0
LICENSINGBASISPCT+PCTASSESSMENTS PCT=
2012
Serial Number21-183 Docket Nos.50-280/281 Attachment 4
Page6of7 10CFR 50.46 MARGIN UTILIzATION
- WESTINGHOUSE LARGEBREAKLOCA Plant Name:
Surry PowerStation, Unit2 Utility Name:
VirginiaElectric andPowerCompany An.a.lysisJnfomation EM:
ASTRUM (2004) Limiting BreakSize:DEG Analysis Date:
10/6/2010 Vendor:
Westinghouse FQ:
2.5 FAH:
1.7 Fuel:
Upgrade SGTP(%): 7 Notes:
None M
LICENSINGBASIS Analysis ofRecord PCT 1853 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
Evaluation ofFuel Pellet Thermal Conductivity 183 Degradation 2.
Pellet Radial Profile Option
-13 3.
HOTSPOT Burst Temperature Calculation 0
forzIRLOCladding 4.
RodInternal Pressure Calculation 0
5.
HOTSPOT Iteration Algorithm forCalculating the 0
Initial Fuel Pellet Average Temperature 6.
WCOBRA/TRAC Thermal-Hydraulic History File 0
Dimension usedinHSDRIVERBackground 7.
WCOBRA/TRAC Automated Restart Process Logic Error 0
8.
Initial Fuel Pellet Average Temperature Uncertainty 0
Calculation 9.
Elevations forHeatSlab Temperature Initialization0
- 10. HeatTransfer ModelError Corrections 0
- 11. Correction toHeatTransfer NodeInitialization 0
- 12. MassConservation Error Fix 0
- 13. Correction toSplit Channel MomentumEquation 0
- 14. HeatTransfer Logic Correction forRodBurst Calculation 0
- 15. Changes toVessel Superheated SteamProperties 0
- 16. Update toMetal Density Reference Temperatures 0
- 17. DecayHeatModelError Corrections 0
- 18. Correction tothePipe Exit Pressure DropError 0
- 19. WCOBRA/TRAC U19File Dimension Error Correction 0
- 20. Revised HeatTransfer Multiplier Distributions
-7
- 21. HOTSPOTBurst Strain Error Correction 51
- 22. Changes toGridBlockage Ratio andPorosity 0
- 23. GridHeatTransfer Enhancement Calculation 0
- 24. Vessel Section 7Mid-Level Elevation Modeling 0
- 25. Burst Elevation Selection 0
Serial Number 21-183 Docket Nos.50-280/281 Attachment 4
Page7of7 26.
ErrorsinDecay GroupUncertainty Factors 4
27.
Evaluation ofAdditional Containment Metal 0
28.
Error inOxidationCalculations 0
29.
Error inuseofASMESteam Tables 0
30.
Core Barrel Unheated Conductor Errors 0
31.
Discrepancy inWettedPerimeter Inputs 0
32.
Inconsistent Application ofNumerical RampApplied 0
tothe Entrained Liquid /Vapor Interfacial DragCoefficient 33.
InappropriateResetting ofTransverseLiquid MassFlow0
- 34. Steady-State FuelTemperature CalibrationMethod 0
- 35. Vapor TemperatureResetting 0
36.
Removal oftheVessel Interfacial HeatTransfer Limit 0
B.
Planned Plant Modification Evaluations 1.
None 0
C.
2020ECCSModelAssessments l.
None 0
D.
Other l
None 0
LICENSING BASISPCT+PCTASSESSMENTS PCT =
2071
Attachment 5
2020ANNUALREPORTOF EMERGENCY CORE PURSUANT TOTHEREQUIREMENTS OF10CFR50.46 2020ANNUALREPORTING OF10CFR50.46 MARGIN UTlLlzATION DOMINION ENERGYSOUTHCAROLINA, INC.
VIRGlL C.SUMMERNUCLEARSTATIONUNIT1
Serial Number21-183 Docket Nos.50-395 Attachment 5
Page2of11 Plant Name:
V.C.Summer Utility Name:
Dominion Energy South Carolina Ah EM: NOTRUMP Limiting BreakSize:3 Inch Analysis Date:
February 2003 Vendor:
Westinghouse FQ: 2.45FdH: 1.62 Notes:
None Clad.[em.p.EF)
LICENSINGBASIS Analysis ofRecord PCT 1775 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1
NOTRUMP-EM Refined Break Spectrum 0
2.
Errors inReactor Vessel Nozzle Data Collections 0
3.
PumpWeirResistance Modeling 0
4 Errors inReactor Vessel LowerPlenum Surface AreaCalculations 0
5.
Modeling ofAnnular Pellets 0
6.
Discrepancy inMetal Masses UsedFromDrawings 0
7.
V.C.SummerUpflow Conversion 148 8.
Treatment ofVessel Average Temperature Uncertainty 0
9.
Urania-Gadolinia Pellet Thermal Conductivity Calculation 0
- 10. Pellet Crack andDishVolumeCalculation 0
- 11. Radiation HeatTransfer Logic 0
- 12. MaximumFuelRodTimeStep Logic 0
- 13. NOTRUMP-EM Evaluation ofFuelPellet Thermal Conductivity Degradation 0
- 14. SBLOCTACladding Strain Requirement forFuel RodBurst 0
- 15. Fuel RodGapConductance Error 0
- 16. Radiation HeatTransfer ModelError 0
- 17. SBLOCTAPre-DNBCladding Surface HeatTransfer Coefficient Calculation 0
- 18. Control RodDropTimeTechnical Specification Change 0
- 19. Vessel Average Temperature Uncertainty 0
- 20. Error intheUpper Plenum Fluid VolumeCalculation 0
- 21. UO2FuelPellet HeatCapacity 0
B.
Planned Plant Modification Evaluations 1
None 0
C.
2020ECCSModelAssessments
Serial Number21-183 Docket Nos.50-395 Attachment 5
Page3of11 1.
Increased Vessel Average Temperature Uncertainty 0
D.
Other 1.
None 0
LICENSING BASIS PCT +PCTASSESSMENTS PCT=
1923
Serial Number 21-183 Docket Nos.50-395 Attachment 5
Page4of11 Plant Name:
V.C.Summer Utility Name:
Dominion Energy South Carolina Analysisinformation EM: CQD (1996)
Limiting BreakSize:
DEGB Analysis Date:
February 2003 Vendor:
Westinghouse FQ: 2.5 FdH:1.7 Notes:
None
.ChLdTemp.fFj LICENSINGBASIS Analysis ofRecord PCT 1860 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
FanCooler Performance Increase 0
2.
Improved Automation ofEndofBlowdown Time 0
3.
Implementation ofASTRUMCapability inHOTSPOT 0
4 Revised Blowdown Heatup Uncertainty Distribution 49 5.
Revised Iteration Algorithm forCalculating TheAverage FuelTemperature 0
6.
Improved Automation ofEndofBlowdown Time 0
7.
Thermodynamic Properties fromThermo 0
8.
Pressurizer Fluid Volumes 0
9.
Vessel Unheated Conductor Noding 0
- 10. Containment Relative Humidity Assumption 0
- 11. HOTSPOT Fuel Relocation 0
- 12. SteamGenerator Nozzle Volume Accounting Error 0
- 13. ColdLegVolume Discrepancy 0
- 14. Errors inReactor Vessel Nozzle DataCollection 0
- 15. HOTSPOTBurst Temperature Logic Errors 0
- 16. V.C.SummerUpflow Conversion
-7
- 17. zero Cross-Flow Boundary Condition Error 0
- 18. Discrepancy inMetal Masses UsedFromDrawings 0
- 19. HOTSPOTGapHeatTransfer Logic 0
- 20. HOTSPOTStatistical Output Logic 0
- 21. Treatment ofVessel Average Temperature Uncertainty 0
- 22. Additional HeatSinks andMaximumSpray Flow 0
- 23. Fuel Pellet Thermal Conductivity Degradation andPeaking Factor Burndown 0
- 24. PAD4.0Implementation
-83
- 25. zero Cross-Flow Boundary Condition Error 0
- 26. HOTSPOTBurst Temperature Calculation ForzIRLOCladding 0
- 27. HOTSPOTIteration Algorithm forCalculating TheInitial Fuel Pellet Average Temperature 0
Serial Number 21-183 Docket Nos.50-395 Attachment 5
Page5of11 28.
WCOBRA/TRAC Automated Restart Process Logic Error 0
29.
RodInternalPressure Calculation 0
30.
WCOBRA/TRAC Thermal-HydraulicHistory File Dimension usedinHSDRIVER 0
31.
Burst Elevation Selection 0
32.
Elevation forHeatSlab Temperature Initialization 0
- 33. Heat Transfer Logic forRodBurst Calculation 0
34.
WCOBRA/TRAC Ul9File Dimension Error Correction 0
- 35. Heat TransferModel ErrorCorrections 0
- 36. Correction toHeat Transfer NodeInitialization 0
- 37. MassConservationError Fix 0
- 38. Correction toSplit Channel Momentum Equation 0
- 39. Changes toVessel Superheated Steam Properties 0
- 40. Update toMetal Density Reference Temperatures 0
41 DecayHeatModelError Correction 0
- 42. Correction tothePipe Exit Pressure Drop Error 0
- 43. Vessel Section 7Mid-Level Elevation Modeling 0
- 44. Grid HeatTransfer Enhancement Calculation 0
- 45. Revised HeatTransfer Multiplier Distributions
-5
- 46. Changes toGridBlockage Ratio andPorosity 0
- 47. Error inBurst Strain Application 0
- 48. CodeUncertainty inBELBLOCAMonteCarlo Simulations 0
- 49. Error inOxidation Calculations 0
- 50. Support Column Unheated Conductor Error 0
51 Vessel Average Temperature Uncertainty 0
- 52. Numerical RampEntrained Liquid/Vapor Interfacial Drag 0
- 53. Inappropriate Resetting ofTransverse Liquid MassFlow 0
- 54. Vapor Temperature Resetting 0
- 55. Removal oftheVessel Interfacial HeatTransfer Limit 0
B.
Planned Plant Modification Evaluations 1
None 0
C.
2020ECCSModelAssessments 1.
Increased Vessel Average Temperature Uncertainty 0
D.
Other 1
None 0
LICENSING BASISPCT+PCTASSESSMENTS PCT=
1814
Serial Number 21-183 Docket Nos.50-395 Attachment 5
Page6of11 Plant Name:
V.C.Summer Utility Name:
Dominion Energy South Carolina Ag1aly.sisinformatio!1 EM: CQD (1996)
Limiting BreakSize:DEGB Analysis Date:
February 2003 Vendor:
Westinghouse FQ: 2.5 FdH: 1.7 Notes:
None h
LICENSING BASIS Analysis ofRecord PCT 1808 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
FanCooler Performance Increase 1
2.
Improved Automation ofEndofBlowdown Time 0
3.
Implementation ofASTRUMCapability inHOTSPOT 0
4 Revised Blowdown Heatup Uncertainty Distribution 5
5.
Revised Iteration Algorithm forCalculating TheAverage FuelTemperature 0
6.
Improved Automation ofEndofBlowdown Time 0
7.
Thermodynamic Properties fromThermo 0
8.
Pressurizer Fluid Volumes 0
9.
Vessel Unheated Conductor Noding 0
- 10. Containment Relative Humidity Assumption 0
11 HOTSPOTFuel Relocation 0
- 12. SteamGenerator Nozzle Volume Accounting Error 0
- 13. ColdLegVolumeDiscrepancy 0
- 14. Errors inReactor Vessel Nozzle DataCollection 0
l5.
HOTSPOTBurst Temperature Logic Errors 0
- 16. V.C.SummerUpflow Conversion
-44
- 17. zero Cross-Flow Boundary Condition Error 0
- 18. Discrepancy inMetal Masses UsedFromDrawings 0
- 19. HOTSPOTGapHeatTransfer Logic 0
- 20. HOTSPOTStatistical Output Logic 0
- 21. Treatment ofVessel Average Temperature Uncertainty 0
- 22. Additional HeatSinks andMaximumSpray Flow 0
- 23. Fuel Pellet Thermal Conductivity Degradation andPeaking Factor Burndown I13
- 24. PAD4.0Implementation
-118
- 25. zero Cross-Flow Boundary Condition Error 0
- 26. HOTSPOT Burst Temperature Calculation ForzIRLOCladding 0
- 27. HOTSPOTIteration Algorithm forCalculating TheInitial Fuel Pellet Average Temperature 0
Serial Number 21-183 Docket Nos.50-395 Attachment 5
Page7of11 28.
WCOBRA/TRAC Automated Restart Process Logic Error 0
29.
RodInternalPressure Calculation 0
30.
WCOBRA/TRAC Thermal-HydraulicHistory File Dimension usedinHSDRIVER 0
31.
Burst Elevation Selection 0
32.
Elevation forHeatSlab Temperature Initialization 0
- 33. Heat Transfer Logic forRodBurst Calculation 0
34.
WCOBRA/TRAC Ul9File Dimension Error Correction 0
- 35. HeatTransferModel ErrorCorrections 0
- 36. Correction toHeat Transfer NodeInitialization 0
- 37. MassConservationError Fix 0
- 38. Correction toSplit Channel Momentum Equation 0
- 39. Changes toVessel Superheated Steam Properties 0
- 40. Update toMetal Density Reference Temperatures 0
- 41. Decay HeatModelError Correction 0
- 42. Correction tothePipe Exit Pressure Drop Error 0
- 43. Vessel Section 7Mid-Level Elevation Modeling 0
44 GridHeatTransfer Enhancement Calculation 0
- 45. Revised HeatTransfer Multiplier Distributions 5
- 46. Changes toGridBlockage Ratio andPorosity 24
- 47. Error inBurst Strain Application 20
- 48. CodeUncertainty inBELBLOCAMonteCarlo Simulations 0
- 49. Error inOxidation Calculations 0
50 Support ColumnUnheated Conductor Error 0
- 51. Vessel Average Temperature Uncertainty 0
- 52. Numerical RampEntrained Liquid/Vapor Interfacial Drag 0
- 53. Inappropriate Resetting ofTransverse Liquid MassFlow 0
- 54. Vapor Temperature Resetting 0
- 55. Removal oftheVessel Interfacial HeatTransfer Limit 0
B.
Planned Plant Modification Evaluations 1.
None 0
C.
2020ECCSModelAssessments l.
Increased Vessel Average Temperature Uncertainty 0
D.
Other 1.
None 0
LICENSING BASISPCT+PCTASSESSMENTS PCT=
1814
Serial Number 21-183 Docket Nos.50-395 Attachment 5
Page8of11 Plant Name:
V.C.Summer Utility Name:
Dominion Energy South Carolina An.alyjs.Informa.tion EM: CQD (1996)
Limiting BreakSize:
DEGB Analysis Date:
February 2003 Vendor:
Westinghouse FQ: 2.5 FdH:1.7 Notes:
None h
LICENSINGBASIS Analysis ofRecord PCT 1988 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1.
FanCooler Performance Increase 2
2.
Improved Automation ofEndofBlowdown Time 0
3.
Implementation ofASTRUMCapability inHOTSPOT 0
4 Revised Blowdown Heatup Uncertainty Distribution 5
5.
Revised Iteration Algorithm forCalculating TheAverage Fuel Temperature 0
6.
Improved Automation ofEndofBlowdown Time 0
7.
Thermodynamic Properties fromThermo 0
8.
Pressurizer Fluid Volumes 0
9.
Vessel Unheated Conductor Noding 0
- 10. Containment Relative Humidity Assumption 0
11 HOTSPOT Fuel Relocation 0
- 12. Steam Generator Nozzle VolumeAccounting Error 0
- 13. ColdLegVolume Discrepancy 0
- 14. Errors inReactor Vessel Nozzle DataCollection 0
- 15. HOTSPOTBurst Temperature Logic Errors 0
- 16. V.C.SummerUpflow Conversion
-29
- 17. zero Cross-Flow Boundary Condition Error 0
- 18. Discrepancy inMetal Masses UsedFromDrawings 0
- 19. HOTSPOTGapHeatTransfer Logic 0
- 20. HOTSPOTStatistical Output Logic 0
- 21. Treatment ofVessel Average Temperature Uncertainty 0
- 22. Additional HeatSinks andMaximumSpray Flow 1
- 23. FuelPellet Thermal Conductivity Degradation andPeaking Factor Burndown 123
- 24. PAD4.0Implementation
-118
- 25. zero Cross-Flow Boundary Condition Error 0
- 26. HOTSPOTBurst Temperature Calculation ForzIRLOCladding 0
- 27. HOTSPOTIteration Algorithm forCalculating TheInitial FuelPellet Average Temperature 0
Serial Number21-183 Docket Nos.50-395 Attachment 5
Page9of11 28.
WCOBRA/TRAC Automated Restart Process Logic Error 0
29.
RodInternalPressure Calculation 0
30.
WCOBRA/TRAC Thermal-HydraulicHistory File Dimension usedinHSDRIVER 0
31 Burst Elevation Selection 0
32.
Elevation forHeatSlab Temperature Initialization 0
- 33. Heat Transfer Logic forRodBurst Calculation 0
34.
WCOBRA/TRAC U19File Dimension Error Correction 0
- 35. HeatTransferModel ErrorCorrections 0
- 36. Correction toHeat Transfer NodeInitialization 0
- 37. MassConservationError Fix 0
- 38. Correction toSplit Channel Momentum Equation 0
- 39. Changes toVessel Superheated Steam Properties 0
- 40. Update toMetal Density Reference Temperatures 0
- 41. Decay HeatModelError Corrections 0
- 42. Correction tothePipe Exit Pressure Drop Error 0
- 43. Vessel Section 7Mid-Level Elevation Modeling 0
- 44. Grid HeatTransfer Enhancement Calculation 0
- 45. Revised HeatTransfer Multiplier Distributions
-35
- 46. Changes toGridBlockage Ratio andPorosity 24
- 47. Error inBurst Strain Application 0
- 48. CodeUncertainty inBELBLOCAMonteCarlo Simulations 0
- 49. Error inOxidation Calculations 0
- 50. Support Column Unheated Conductor Error 0
- 51. Vessel Average Temperature Uncertainty 0
- 52. Numerical RampEntrained Liquid/Vapor Interfacial Drag 0
- 53. Inappropriate Resetting ofTransverse Liquid MassFlow 0
- 54. Vapor Temperature Resetting 0
- 55. Removal oftheVessel Interfacial HeatTransfer Limit 0
B.
Planned Plant Modification Evaluations 1.
None 0
C.
2020ECCSModelAssessments 1.
Increased Vessel Average Temperature Uncertainty 0
D.
Other 1.
None 0
LICENSING BASISPCT+PCTASSESSMENTS PCT=
1961
Serial Number21-183 Docket Nos.50-395 Attachment 5
Page10of11 Plant Name:
V.C.Summer Utility Name:
Dominion Energy South Carolina AnalysiIn[orm.ation EM: CQD (1996)
Limiting BreakSize:DEGB Analysis Date:
February 2003 Vendor:
Westinghouse FQ: 2.5 FdH:1.7 Notes:
None CjadTempfU LICENSINGBASIS Analysis ofRecord PCT 1988 PCTASSESSMENTS (Delta PCT)
A.
Prior ECCSModelAssessments 1
FanCooler Performance Increase 2
2.
Improved Automation ofEndofBlowdown Time 0
3.
Implementation ofASTRUMCapability inHOTSPOT 0
4 Revised Blowdown Heatup Uncertainty Distribution 5
5.
Revised Iteration Algorithm forCalculating TheAverage FuelTemperature 0
6.
Improved Automation ofEndofBlowdown Time 0
7.
Thermodynamic Properties fromThermo 0
8.
Pressurizer Fluid Volumes 0
9.
Vessel Unheated Conductor Noding 0
- 10. Containment Relative Humidity Assumption 0
- 11. HOTSPOTFuel Relocation 0
- 12. SteamGenerator Nozzle Volume Accounting Error 0
- 13. ColdLegVolume Discrepancy 0
- 14. Errors inReactor Vessel Nozzle DataCollection 0
- 15. HOTSPOTBurst Temperature Logic Errors 0
- 16. V.C.SummerUpflow Conversion
-29
- 17. zero Cross-Flow Boundary Condition Error 0
- 18. Discrepancy inMetal Masses UsedFromDrawings 0
- 19. HOTSPOT GapHeatTransfer Logic 0
- 20. HOTSPOTStatistical Output Logic 0
- 21. Treatment ofVessel Average Temperature Uncertainty 0
- 22. Additional HeatSinks andMaximumSpray Flow 1
- 23. FuelPellet Thermal Conductivity Degradation andPeaking Factor Burndown 123
- 24. PAD4.0Implementation
-118
- 25. zero Cross-Flow Boundary Condition Error 0
- 26. HOTSPOTBurst Temperature Calculation ForzIRLOCladding 0
- 27. HOTSPOTIteration Algorithm forCalculating TheInitial Fuel Pellet Average Temperature 0
Serial Number21-183 Docket Nos.50-395 Attachment 5
Page11of11 28.
WCOBRA/TRAC Automated Restart Process Logic Error 0
29.
RodInternalPressure Calculation 0
30.
WCOBRA/TRAC Thermal-HydraulicHistory File Dimension usedinHSDRIVER 0
31 Burst Elevation Selection 0
32.
Elevation forHeatSlab Temperature Initialization 0
- 33. Heat Transfer Logic forRodBurst Calculation 0
34.
WCOBRA/TRAC Ul9File Dimension Error Correction 0
- 35. HeatTransferModel ErrorCorrections 0
- 36. Correction toHeat Transfer NodeInitialization 0
- 37. MassConservationError Fix 0
- 38. Correction toSplit Channel Momentum Equation 0
- 39. Changes toVessel Superheated Steam Properties 0
- 40. Update toMetal Density Reference Temperatures 0
- 41. DecayHeatModel Error Correction 0
41 Correction tothePipeExit Pressure Drop Error 0
- 42. Vessel Section 7Mid-Level Elevation Modeling 0
- 43. Grid HeatTransfer Enhancement Calculation 0
- 44. Revised HeatTransfer Multiplier Distributions
-35
- 45. Changes toGridBlockage Ratio andPorosity 24
- 46. Error inBurst Strain Application 0
- 47. CodeUncertainty inBELBLOCAMonteCarlo Simulations 0
- 48. Error inOxidation Calculations 0
- 49. Support Column Unheated Conductor Error 0
- 50. Vessel Average Temperature Uncertainty 0
- 51. Numerical RampEntrained Liquid/Vapor Interfacial Drag 0
- 52. Inappropriate Resetting ofTransverse Liquid MassFlow 0
- 53. Vapor Temperature Resetting 0
- 54. Removal oftheVessel Interfacial HeatTransfer Limit 0
B.
Planned Plant Modification Evaluations 1
None 0
C.
2020ECCSModelAssessments 1
Increased Vessel Average Temperature Uncertainty 0
D.
Other 1.
None 0
LICENSINGBASISPCT+PCTASSESSMENTS PCT=
1961
.