ML15005A130

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Meeting Slide Re. Browns Ferry Nuclear Plant - Extended Power Uprate License Amendment Request Approach to Treatment of Hydrogen Embrittlement Issue
ML15005A130
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 01/15/2015
From:
Tennessee Valley Authority
To: Farideh Saba
Plant Licensing Branch II
Saba F DORL/LPL2-2 301-415-1447
References
Download: ML15005A130 (14)


Text

BrownsFerryNuclearPlant ExtendedPowerUprateLicenseAmendmentRequest ApproachtoTreatmentofHydrogenEmbrittlement Issues January15,2015

Agenda

Introductions

OverviewandSchedule 10CFR50.46cRulemaking Proposed10CFR50.46cComplianceActivities andTimeline Treatmentof10CFR50.46cIssuesinExtended PowerUprateLicenseAmendmentRequest ReactivityInitiatedAccidentIssues AcronymList Questions/Comments G. Doyle G.Doyle T.Eichenberg T.Eichenberg T.Eichenberg T.Eichenberg G. Doyle 2

OverviewandSchedule 3

  • NewconsolidatedBrownsFerryExtendedPower Uprate(EPU)LicenseAmendmentRequest(LAR) submittal
  • SupersedespreviousBrownFerryEPUsubmittals

- AddressescurrentBrownsFerryconditionsandlicensingbasis (e.g.,AREVAATRIUM10XMfueltype)

  • UsestheformatofRS001,ReviewStandardforExtended PowerUprates
  • AddressespreviousapplicableNRCRequestsforAdditional Information(RAIs)
  • Appliesimprovedsubmittalverificationprocesstoensure completenessandaccuracy
  • Weareheretopresentanddiscussourpositionfor addressinghydrogenembrittlement issuesinorderto precludeimpacttotheBrownsFerryEPULARreview
  • Proposed10CFR50.46crulemaking
  • ProposedReactivityInitiatedAccidentguidancerevision

OverviewandSchedule(continued) 4

10CFR50.46cRulemaking 5

- RevisesEmergencyCoreCoolingSystems(ECCS) acceptancecriteriainlightof:

  • NUREG6967/CRresearchfindings Betalayerembrittlementbyoxygen/Betalayerthinning LocalizedHydrogeninducedembrittlementinballoonregion Hydrogenenhancedbetalayerembrittlementbyoxygen Generalhydrogeninducedembrittlementfrombreakawayoxidation Oxygenpickupfromthecladdinginnersurface
  • PetitionsforRulemaking(PRM)

PRM5071-eliminateZIRLO'fromrulelanguage PRM5084-effectsofcrudandoxidelayers

  • Longtermcooling
  • Riskinformedalternative/GenericSafetyIssue(GSI)191related BoilingWaterReactor(BWR)RelatedLetter

10CFR50.46cRulemaking(continued) 6

  • Rulemakingissuesnotimmediatesafetyconcern

- BWROwnersGroupMarginAssessment[(BWROG)TP11010]

  • OperabilityTypeAnalysis

- Notintendedtobealicensingbasisanalysis

- AppliedtoBWRcurrentoperatingfleet

- SupportedthatRulemakingcanmoveforwardonnormalschedule

  • BrownsFerryaddressedinthereport
  • DraftRulePublishedSpring2014

- PublicCommentsPeriodClosedAugust21,2014

- TennesseeValleyAuthorityparticipatedinthedevelopmentofthe Industrycomments

  • FinalPublicationPossibleasearlyasSpring2016

- NewrulepotentiallyeffectiveduringEPULARreviewperiod

  • Underthesecircumstances,NRChasindicateddocketedLARs(involving LOCA)mustbeincompliancewithnewrulepriortofinalapproval
  • However,draftrulehasanextendedimplementationscheduleafterthe finalrulepublicationdate

Based,inpart,onresultsofBWROGTP11010

10CFR50.46cComplianceScope 7

BasedonCurrentProposed10CFR50.46c DevelopthefollowingMethodologyReports

- FuelRodThermalMechanicalMethod

Hydrogenuptakemodel

CrudandPreoxidation

- ECCSPerformanceMethod

CathcartPaweltimeattemperaturecorrelation

Interioroxygenuptake

- LongTermCoolingMethod

Unknownrequirementtoday PerformanceandAcceptancemethodsfromscratch

Deterministicdebrismodelforalltimeframes Performancemethodsandacceptancecriteriadevelopment IntersectionwithGSI191relatedprograms

Performfurthermaterialtesting DevelopVendorBreakawayOxidationProgram TechnicalSpecification(TS)5.6.5,CoreOperatingLimitsReport(COLR),

LAR

- ReflectnewCOLRmethodssatisfying10CFR50.46c NRCpriorapprovaloftheaboveactivitiesisrequired

10CFR50.46cComplianceTimeline 8

FinalcompliancetosupportEPULARreviewscheduleisanunrealisticexpectation

Treatmentof10CFR50.46cIssuesinEPULAR 9

  • BrownsFerryUptoDateMarginAssessment

- AdditionalAnalysesatEPUConditions

  • Complimentexistingmarginassessmentreport
  • SeparateBrownsFerryanalyses,notpartofBWROG

- SpecificChangesRelativetoExistingMarginReport

  • AutomaticDepressurizationSystem(ADS)

Initiationlogicnowsinglefailureproof

  • Topdowncorespraylicensingbasisrequirements MethodologyassupplementedbyNRCsafetyevaluationsdatedApril27,2012,and February15,2013
  • ATRIUM10XMfuel
  • 120%OLTPpowerlevel

Treatmentof10CFR50.46cIssuesinEPULAR (continued) 10 AdditionalAssessmenttoInclude HydrogenPickupEffects ResultswithmodelusedforBWROGTP11010

FRAPCONZr2AlloyHydrogenuptakemodel

[K.GeelhoodandC.Beyer,CorrosionandHydrogenPickupModelinginZirconiumBasedAlloys,PaperNo.8145,Proceedingsofthe2008Water ReactorFuelPerformanceMeeting,October1923,Seoul,Korea(2008)]

ResultswithAREVAmodelcurrentlydocketedforNRCreview

[BAW10247PAR0,Supplement1PR0]

Norequestofplantspecifichydrogenuptakemodelapproval MaximumEquivalentCladdingReacted(ECR)results PeakCladdingTemperaturelimitedbreak

ApplyingCathcartPaweltimeattemperature(2200°Fexperimentalbasis)

Relevantbreakawayoxidationtimeinformation LongTermCoolingAddressedByExistingMethod

[NEDO20566A,AnalyticalModelforLossofCoolantAnalysisinAccordancewith10CFRAppendixK]

TreatmentofLegacyATRIUM10Fuel Legacyfuelshouldbegrandfathered Lastdeliveredreloadisalreadybeingirradiated Fuelwillbelowpowerduringtransition UptodateMarginAssessmentwillprovidereasonableassurance BrownsFerrywillbeabletomeetfinal10CFR50.46crequirementsat EPUconditions

ReactivityInitiatedAccidentIssues 11 ReactivityInitiatedAccident(RIA)

- Plantspecificresponsesneededtoaddressemergingconcerns

  • NoRegulatoryGuidanceorStandardReviewPlanwithfinalcriteria
  • Approvedmethodsarenotinplaceyettoaddressallemergingissues
  • Potentialforunderstandingofphenomena,NRCfocusofconcern, andmethodsofevaluationtoevolveovertime

- NRCpapersuggeststhatemergingRIAissueswillbeaddressedin RAIprocess Ifanexistinglicenseevoluntarilyseeksalicenseamendmentorchangeand (1)theNRCstaffsconsiderationoftherequestinvolvesaregulatoryissue directlyrelevanttoRIAand(2)thespecificsubjectmatterofthisnew guidanceisanessentialconsiderationinthestaffsdeterminationofthe acceptabilityofthelicenseesrequest,thenthestaffmayrequestthatthe licenseeeitherfollowthenewguidanceorprovideanequivalentalternative processthatdemonstratescompliancewiththeunderlyingNRCregulatory requirements.(TheU.S.NuclearRegulatoryCommissionsStrategyforRevisingthe RIAAcceptanceCriteria,Proceedingsofthe2012TopFuelReactorFuelPerformance Meeting,Manchester,UnitedKingdom,September26,2012,PaperA0112)

ReactivityInitiatedAccidentIssues(continued) 12 ReactivityInitiatedAccident

- RIACriteriathatwillbesupportedbyLAR

  • Showthatthecurrentradiologicalsourceevaluationboundsthe numberofrodsfailedbasedonpeakradialaveragefuelenthalpyrise criteriaof170cal/g[highcladdingtemperaturefailurecriteriaforzeropowerconditions, currentlyapprovedBrownsFerrymethodology:SER for ANF-89-98(P)(A), Revision 1, Generic Mechanical Design Criteria]
  • Showinterimcriteriaforcorecoolabilityof230cal/gpeakaverage fuelenthalpyriseismet

- BrownsFerryDesignBasisiscurrently280cal/g[SER for ANF-89-98(P)(A),

Revision 1, Generic Mechanical Design Criteria]

- CompliancewithotheremergingNRCRIAregulatory requirementswillbedemonstratedasrequestedduringRAI process

  • ApproachtoRIAConsistentwithCurrentNRCExpectation

AcronymList ADS-AutomaticDepressurizationSystem AOR-AnalysisofRecord BWR-BoilingWaterReactor BWROG-BWROwnersGroup CFR-CodeofFederalRegulation COLR-CoreOperatingLimitsReport ECCS-EmergencyCoreCoolingSystems ECR-EquivalentCladdingReacted EPU-ExtendedPowerUprate FRN-FederalRegisterNotice GSI-GenericSafetyIssue LAR-LicenseAmendmentRequest LOCA-LossofCoolantAccident LTR-LicensingTopicalReport NRC-NuclearRegulatoryCommission OLTP-OriginalLicensedThermalPower PRM-PetitionforRulemaking RAI-RequestforAdditionalInformation RIA ReactivityInitiatedAccident TS-TechnicalSpecifications 13

14 Questions/Comments