ML20099F241

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Co., NRC Safety Pre& 8208;Application Meeting North Anna Power Station (NAPS)
ML20099F241
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 04/09/2020
From:
Dominion Energy Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20099F240 List:
References
Download: ML20099F241 (22)
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Text

NRC SafetyPreApplication Meeting NorthAnnaPowerStation(NAPS)

April9,2020 1

NorthAnnaOverview

  • Net Capacity: Each unit is
  • ~800 MWnet => 2940MWt
  • SisterPlanttoSurryPowerStation
  • LocatedinLouisaCounty,VA 2

OLs 40Yrs 60Yrs 80Yrs Unit 1 1978 2018 2038 2058 Unit 2 1980 2020 2040 2060

Plant Aerial

DiscussionTopics

  • Sameexperiencedteamusingsamemethodologiesfrom Surry
  • InsightsfromSurrySLRwereincorporatedintotheNorth AnnaSLRAtotheextentpractical
  • CommonalityinplantdesignsandmanyFleetAMPs
  • SafetyportionbasedonNUREG2192,NEI1701,andRG 1.188
  • AgingManagementReviewsperformedwithhighdegreeof consistencywithNUREG2191andrecentNRCdraftISGs
  • AgingManagementProgramsdevelopedtomaximize consistencywithNUREG2191andrecentNRCdraftISGs

IntegratedPlantAssessment NEI1701methodologyutilizedthroughoutIPAprocess NorthAnnamethodologywasconsistentwithSurry:

Revalidationofvariousdesigninputsforinscope determinations

(a)2methodologyconsistentwithcurrentstandardsand expectations HigherdegreeofAMRconsistencywithGALLSLR:

>99%Consistency(only11of7495lineswithFJNotes)

60NoteELines(plantspecificAMPsand/orAMPexceptions) 10YearOESearchidentifiednonewagingeffects GALLSLR comprehensive FERitemsrequiringplantspecificreviewresultedinaging managementconsiderations 5

NewSLRAMPs XI.M32 OneTimeInspection XI.M33 SelectiveLeaching XI.M35 ASMECodeClass1SmallBorePiping XI.E3B InaccessibleInstrumentandControlCables NotSubjectto10CFR50.49 XI.E3C InaccessibleLowVoltagePowerCablesNot Subjectto10CFR50.49 XI.E6 ElectricalCableConnectionsNotSubjectto 10CFR50.49 XI.E7 HighVoltageInsulators 6

AMPsWithExceptions XI.M3ReactorHeadClosureStudBolting Yieldstrengthandultimatetensilestrength(SPS)

XI.M20OpenCycleCoolingWaterSystem RecirculationsprayHTEXtestinterval(SPS)

XI.M27FireWaterSystem Firepumpsuctionstrainer Maindraintestfrequency(SPS)

XI.M29AtmosphericMetallicStorageTanks Caulking/sealantandconcretemissileshield(SPS)

XI.M42InternalCoatings/Linings(ISGTBD) 7

AMPsWithEnhancements

  • 12consistentwithGALL noenhancements
  • 13minimalenhancements:

Scopeand/orstandardGALLlanguageenhancement

4orlessenhancementswithstraightforwardguidanceto beincorporated

  • 11manyenhancements:

>4enhancementstobeincorporated

moreinvolvedenhancementstobeincorporated 8

IncorporationofRevisionstoGALLSLR AMPsXI.M2&XI.M21AEPRIChemistryGuidelines AMPXI.M12ThermalAgingEmbrittlement AMPXI.M16APWRVesselInternals(MRP227R1A)

AMPXI.M42InternalCoatings/Linings AMPXI.E7HighVoltageInsulators AMPXI.S1ASMESectionXI,SubsectionIWE AMPXI.S8ProtectiveCoatings AMRitems:Table3.51 AMRitems:GenericFJNotes(15items) 9

FlawToleranceEvaluationforRCSCASS

  • FlawtoleranceevaluationisconsistentwithGrimessLetterandNUREG 2191SectionXI.M12,ThermalAgingEmbrittlementofCASS
  • EvaluationconsistentwithIWB3640andAppendixCofASMESectionXI.
  • Deltaferriteforcheckchemistryislessthan25%andevaluatedwith ASMESectionXIAppendixCorASMESectionXICodeCaseN838,as applicable,basedondeltaferritecontent
  • TheUnit1crossoverlegdeltaferritecontentperHullsEquivalent FactorsforLadleandCheckchemistryconditionsis24.57%and28.29%.
  • Deltaferriteforoneladlevaluegreaterthan25%isevaluatedusing Category2weldZfactorsfromTableC63301ofthe2019Editionof SectionXI.UseoftheCategory2weldZfactorprovidedinTableC6330 1ofthe2019EditionofSectionXIfordeltaferritegreaterthan25%isa morestringentpenaltyfactorcomparedtotheSAWZfactorfordelta ferritebetween14%and25%.
  • APlantSpecificEvaluationwillbeincludedforassessmentofthefitting withladlevaluegreaterthan25%deltaferrite.

10

ReactorInternalsAMP-FER3.1.2.2.9 80YearReferencebasisfordevelopinganddefiningtheaging managementofPWRreactorvesselinternalscomponents:

MRP191R2(3002013220)Screening,Categorization,Ranking (ML19081A057andML19081A060)

MRP227R1A(3002017168)PWRReactorInternalsInspection andEvaluationGuidelinesincludingNRCSafetyEvaluationand associatedRAIresponses(ML19339G364)

MRP2018022,InterimGuidanceforPWRInternalsI&E Guidelines,MRP227A,forSLR:Westinghouseand CombustionEngineering(ML19081A061)

Recent&relatedIndustryoperatingexperience:

LowerGirthWelds:MRP2019009(ML19249B102)

CRGTSheathsandCTubes:WCAP17451Rev2(ML19262E593) dhd 11

ReactorVessel(RV)SupportSteelConfiguration 12

IrradiationofConcrete:FER3.5.2.2.2.6 FluenceProjections:

Concretebiologicalshield(CBS)fluenceprojectionsat72 EFPYarebelowthefastneutron(E>0.1MeV)fluence thresholdof1x1019 n/cm2 andthegammadosethreshold of1x108 Gy (1x1010 rad)

[WestinghouseProprietaryReport]

CBSConcreteMaximumTemperature:

ThemaximumtemperatureintheCBSconcreteincluding radiationinducedheatingislessthanFER3.5.2.2.2.2limit of200oFforlocalareasand150oFforgeneralareaswith sufficientmargin.

(Gammaheatingreference:EPRITR3002013051) 13

IrradiationofRVSupportSteel NAPSReactorVesselSupportisthroughaNeutronThermal ShieldconfigurationlikeSurry Dominionwillusefracturemechanics(NUREG1509)to demonstratestructuralintegritythroughtheSPEO.

SomedifferencesbetweenSurryandNAPS:

LoadingonNSTforSPSbaseduponFramatomeBreakOpening Time(BOT)previouslyanalyzedforevaluationofthereactorvessel slidefootsupport.

LoadingonNSTforNAPSwillbebaseduponoriginalBOTwhichis overlyconservative.

FracturetoughnessforSPSwasbaseduponKIR/KIa curvewhile thefracturetoughnessforNAPSwillbebasedupontheKIc curve 14

ReactorVesselIntegrity

  • FluenceProjection

RegulatoryGuide1.190

Fluencevaluesupdatedto72EFPY

Extendedbeltlinematerialsidentified

  • MaterialsPropertiesConfirmation

Materialpropertiesreviewedandupdated(PWROG18005 NP)toensureconsistencywithASMECode&BTP53

GenericRotterdamUSE,Cu,NivaluesforRotterdamWelds andForgings(PWROG17090)

LTOP

LTOPenabletemperatureis269F-Systemisenabledper TechnicalSpecificationLCO3.4.12.

  • PressurizedThermalShock(PTS)

RTPTS screeningcriteriavaluessatisfiedthroughSLR(72EFPY) 15

ReactorVesselIntegrity

  • UpperShelfEnergy(USE)

USEvaluesareabove50ftlbs at72EFPYexceptfor

Unit1inletnozzleforging11equalto50ftlbs at72EFPY,and

Unit2intermediateforging04lessthan50ftlbs at72EFPY

EquivalentMarginsAnalysiscompletedbyPWROG19407forUSE itemsandwillbesubmittedforNRCreviewandapproval.

HeatupandCooldownCurves

ConfirmedthatexistingPTcurvesareacceptablethrough72EFPY SurveillanceCapsuleWithdrawSchedule

Letter19390submittedNovember25,2019requestingNRCreview andapprovaltoamendtheSCwithdrawalschedules.

EarlywithdrawaldatescorrespondtothefirstRFOafterwhenthe capsuleswillreachafluenceequalto80yearsoffluence

ForSLR,potentialwithdrawdatescorrespondtothefirstRFOafter whenthecapsuleswillreachafluenceequalto100yearsoffluence.

Reference:

WCAP18363NPandWCAP18364NP 16

EAF-Components&Vessels

  • ASMECodeSectionIIIcomponentsandvessels
  • RetainedallNUREG6260locations
  • Fen methodologyfromNUREG/CR6909
  • NB3200evaluationsreducedCUFandFen multiplierso CUFen belowunity

CRDMs

ReactorVesselinletnozzle,outletnozzleandCETNA

Pressurizerlocations

SteamGeneratorlocations

ReactorCoolantPump

  • FatigueforASMECodeSectionIIIcomponentsmanaged byFatigueMonitoringprogram(cyclecounting)oreddy currenttestingofthesteamgeneratortubing 17

EAF Piping Reactorcoolantloop(RCL)pipingwasdesignedtoUSASB31.7

Pipingclassifiedintothermalzones/transientsections

RetainedallNUREG6260locations

Fen methodologyfromNUREG/CR6909

Onematerialisnotusedtoscreenoutanothermaterial

Commonbasisstressevaluation(EPRI 1024995)usedforonezone

Uen basedupondesigntransientsforonezonewithuseofCodeCaseN779 (Ke)andCodeCaseN902(EPRI3002014121-thicknessandgradientfactors)

Uen basedupondesigntransientsinonezoneusing1979EditionofB31.7 FatigueforUSASB31.7pipingwillbemanagedbyFatigueMonitoringprogram (AppendixL-4locations)

RevisedPressurizerSurgeLineweldinspectionforInitialLicenseRenewal submittedtoNRCinMarch2020 AppendixLinspection(10yearfrequency)forweldthatattachesthereactor coolanthotlegnozzletothepressurizersurgelinepiping Thehotlegnozzletoreactorcoolanthotlegpipingisprotectedbyathermal sleevethusEAFisnotaconcern 18

OtherPlantSpecificTLAAs 3PWROGReportswithNRCSafetyEvaluations genericallyaddressTLAAs

RCPFlywheelFatigueCrackGrowthAnalysis (PWROG17011NPARev2 ML19198A056)

CrackingAssociatedWithWeldDepositedCladding (PWROG17031NPARev1 MLTBD)

ReactorCoolantPumpCodeCaseN481 (PWROG17033NP/PARev1-ML19266A666) 4FirstLicenseRenewalTLAAsdispositionsupdated 1newPlantSpecificTLAAs

SteamGeneratorTubeWearAnalysis 19

DocumentsToBeDocketedWithSLRA PWROG18005NP,Revision2,DeterminationofUnirradiatedRTNDT andUpperShelfEnergyValuesoftheNorthAnnaUnits1and2Reactor VesselMaterials,September2019 WCAP18015NP,Revision2,ExtendedBeltlinePressureVesselFluence EvaluationsApplicabletoNorthAnnUnits1&2,September2018 WCAP18363NP,Rev.1,NorthAnnaUnits1and2Heatup and CooldownLimitCurvesforNormalOperation,March2020 WCAP18353NP,Rev0,ReactorInternalsFluenceEvaluationfora Westinghouse3LoopPlantwithTwoUnits,October2018 WCAP18364NP,Rev.1,NorthAnnaUnits1and2TimeLimitedAging AnalysisonReactorVesselIntegrityforSubsequentLicenseRenewal (SLR),March2020 WCAP11163P,Revision1,TechnicalJustificationforEliminatingLarge PrimaryLoopPipeRuptureastheStructuralDesignBasisforNorthAnna Units1and2NuclearPowerPlantsfortheSubsequentLicenseRenewal Program(80Years)LeakBeforeBreakEvaluation,October2019 20

DocumentsPreviouslyDocketed WCAP14040A,Rev.4,MethodologyUsedtoDevelopColdOverpressure MitigatingSystemSetpointsandRCSHeatup andCooldownLimitCurves,May 2004(ML050120209)

PWROG19047P,NorthAnnaReactorVesselUpperShelfFractureToughness EquivalentMarginAnalysis(MLTBD)

PWROG17011NPA,Revision2,UpdateforSubsequentLicenseRenewal:

WCAP14535A,TopicalReportonReactorCoolantPumpFlywheelInspection EliminationandWCAP15666A,ExtensionofReactorCoolantPumpMotor FlywheelExamination,January,2019(ML19198A056)

PWROG17031NPA,Revision1,UpdateforSubsequentLicenseRenewal:

WCAP15338A,AReviewofCrackingAssociatedwithWeldDepositedCladding inOperatingPWRPlants,May2018(MLTBD)

WCAP15338A,AReviewofCrackingAssociatedwithWeldDepositedCladding inOperatingPWRPlants,October2002(ML083530289)

PWROG17033NPA,Revision1,UpdateforSubsequentLicenseRenewal:

WCAP13045,'CompliancetoASMECodeCaseN481ofthePrimaryLoopPump CasingsofWestinghouseTypeNuclearSteamSupplySystems,'November2019 (ML19266A666) 21

Closing Remarks

  • NorthAnnaisasisterplanttoSurry-ManyFleetAMPs
  • DominionishighlyexperiencedwithSLR
  • Dominionhasbeenengagedandintegratedwiththe developmentofGALLSLRISGsandindustryguidance
  • NorthAnnaSLRAhasincorporatedSurryRAIs
  • NorthAnnaSLRAwillhaveahigherdegreeof consistencywithGALLSLR
  • Dominionwillsubmitahigherqualityapplicationto supportanefficientNRCreview
  • TheNorthAnnaSLRAisaheadofschedulewith expectedsubmittalin3Q20 22
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