ML17229A181

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Application for Amend to License DPR-67,requesting Deletion of Footnote Re TS 2.1.1, Reactor Core Safety Limits.
ML17229A181
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 12/20/1996
From: STALL J A
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17229A182 List:
References
L-96-333, NUDOCS 9612270073
Download: ML17229A181 (13)


Text

CATEGORY1REGULATINFORMATIONDISTRIBUTIONSTEM(RIDS)!'CCFSS.'fONNBR:9612270073DOC.DATE:96/12/20NOTARIZED:NOk'ACIL:50-335St.LuciePlant,Unit1,FloridaPower6LightCo.AUTH,NAMEAUTHORAFFILIATIONSTALL,J.A.FloridaPower&LightCo.RECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)DOCKET05000335

SUBJECT:

ApplicationforamendtolicenseDP$-67,requestingdeletionoffootnotereTS2.1.1,"ReactorCoreSafetyLimits."CDISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionNOTES:RECIPIENTIDCODE/NAMEPD2-3LAWIENS,L.INTERNAL:ACRSNRR/DE/ECGB/ANRR/DRCH/HICBNRR/DSSA/SRXBOGC/HDS3COPIESRECIPIENT.LTTRENCLIDCODE/NAME11PD2-3PD1111F1LECENTER~0111NRR/DE/EMCB11NRR/DSSA/SPLB11NUDOCS-ABSTRACT10COPIESLTTRENCL1111111111EXTERNAL:NOAC11NRCPDR11DNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK/ROOMOWFNSD-5(EXT.415-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR14ENCL,'.13 Cew'tIr,>lC*('I December20,1996FloridaPower8tLightCompany,P.O.Box128,FortPierce,FL34954-0128L-96-33310CFR50.90U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Re:St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment.ReactorCoreSafetLimitPursuantto10CFR50.90,FloridaPower&LightCompany(FPL)requeststoamendFacilityOperatingLicenseDPR-67forSt.LucieUnit1byincorporatingtheattachedTechnicalSpecifications(TS)revision.TheamendmentwilldeleteafootnoteassociatedwithTS2.1.1,"ReactorCoreSafetyLimits,"whichrequiresreactorthermalpowertobelimitedto90%of2700MegawattsthermalforCycle14operationbeyond7000EffectiveFullPowerHours.Itisrequestedthattheproposedamendment,ifapproved,beissuedpriortoMay15,1997topermitcontinuedoperationofSt.LucieUnit1atfullpower.Attachment1isanevaluationoftheproposedTSchange.Attachment2isthe"DeterminationofNoSignificantHazardsConsideration."Attachment3containsacopyoftheaffectedTSpagemarked-uptoshowtheproposedchanges.EnclosedwiththissubmittalisacopyofreportEMF-96-176,"St.LucieUnit1SmallBreakLOCAAnalysiswith30%SteamGeneratorTube.Plugging,"SiemensPowerCorporation,Revision1,December1996.TheproposedamendmenthasbeenreviewedbytheSt.LucieFacilityReviewGroupandtheFloridaPower8.LightCompanyNuclearReviewBoard.Inaccordancewith10CFR50.91(b)(1),acopyoftheproposedamendmentisbeingforwardedtotheStateDesigneefortheStateofFlorida.Pleasecontactusifthereareanyquestionsaboutthissubmittal.Verytrulyyours,J.A.StallVicePresidentSt.LuciePlantJAS/RLDAttachments9hi22700739hi220PDR,ADQCK05000335PPDRPOD((StewartD.Ebnctcr,RegionalAdministrator,RegionII,USNRC.SeniorResidentInspector,USNRC,St.LucicPlant.Mr.W.A.Passctti,FloridaDcpartmcntofHealthandRchabilitativcScrviccs.anFPLGroupcompany 0r<t4 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentReactorCoreSafetLimitSTATEOFFLORIDA))ss.COUNTYOFST.LUCIE)J.A.Stallbeingfirstdulysworn,deposesandsays:ThatheisVicePresident,St.LuciePlant,fortheNuclearDivisionofFloridaPowerEcLightCompany,theLicenseeherein;Thathehasexecutedtheforegoingdocument;thatthestatementsmadeinthisdocumentaretrueandcorrecttothebestofhisknowledge,informationandbelief,andthatheisauthorizedtoexecutethedocumentonbehalfofsaidLicensee.J.A.StallSTATEOFFLORIDACOUNTYOFST.~uc<<Sworntoandsubscribedbeforemethis~~dayofDKCFwR8R19+kbyJ.A.Stall,whoispersonallyknowntome.(DScASignatureofNotaryPublic-StateofFloridao~pSs~sg~~ii~01%C,hnrtcs'D.>dfNameofNotaryPublic(Print,Type,orStamgiig(7sjj8~,ii"'>llillla'l>>

tlI4II1~~'>fe>~'k4 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentReactorCoreSafetLimitATTACHMENT1EVALUATIONOFPROPOSEDCHANGES lI(IjhV4 L-96-333Attachment1P~aeIEVALUATIONOFPROPOSEDTSCHANGESIntroductionTheproposedamendmenttoFacilityOperatingLicenseDPR-67forSt.LucieUnit1willdeleteafootnoteassociatedwithTechnicalSpecification(TS)2.1.1,"ReactorCoreSafetyLimits,"whichrequiresthermalpowertobelimitedtolessthanorequalto90%of2700Megawattsthermal(MWth)forCycle14operationbeyond7000EffectiveFullPowerHours(EFPH).ThethermalpowerconstraintwasimposedinlieuofperformingaSmallBreakLossofCoolantAccident(SBLOCA)re-analysisforfullpoweroperationthatdemonstratesacceptableresultsusinginputassumptionscorrespondingto30%(average)ofallsteamgeneratortubesplugged(SGTP).Thatanalysishasbeencompleted,andareportofanalysisresultsisenclosedwiththissubmittal.DescritionofProosedChaneTS211Pae2-1:Deletetheasteriskfollowing"THERMALPOWER,"anddeletefootnote"*"shownatthebottomofpage2-1.AcopyofTSPage2-1,marked-uptoshowtheproposedchanges,iscontainedinAttachment3.BackroundAmendmentNo.145toFacilityOperatingLicenseNo.DPR-67(L.A.Wiens(NRC)toT.F.Plunkett(FPL):ST.LUCIEUNIT1-ISSUANCEOFAMENDMENTRE:THERIVfALMARGINANDREACTORCOOLANTSYSTEMFLOWLIMITS(TACNO.M95472),July9,1996)wasissuedtopermitplantoperationwithupto30%(average)SGTPand345,000gpmminimumReactorCoolantSystem(RCS)flow.Insupportofthisamendment,FPLhaddeterminedthatconservatismintheexistingSBLOCAanalysis,whichhadpreviouslybeenperformedforconditionscorrespondingto25%SGTPand355,000gpmRCSflow,wouldoffsetanyadverseeffectsduetotheincreasedSGTPanddecreasedreactorcoolantsystemflowforfullpoweroperationupto7000EFPH.Tooffsetanyadverseeffectsforoperationbeyond7000EFPH,itwasdeterminedthatlimitingcorethermalpowerto90%ofratedthermalpowerwouldprovidesufficientmargintoensure10CFR50.46conformityfortheremainderofoperatingCycle14.SubsequenttoissuanceofAmendmentNo.145,are-analysisoftheSBLOCAhasbeencompletedusinginputassumptionscorrespondingto30%(average)SGTPand345,000gpmRCSflow.Theresultsofthatanalysisarebrieflydiscussedinthisevaluation,anddataisprovidedingreaterdetailintheenclosedSiemensPowerCorporation-NuclearDivisionReportEMF-96-176,"St.LucieUnit1SmallBreakLOCAAnalysiswith30%SteamGeneratorTubePlugging,"Revision1,December1996.

L-96-333Attachment1P~ee2BasesforTSChaneByAmendmentNo.145,theNRCapprovedalicenseamendmenttoreducetheRCSflowfrom355,000gpmto345,000gpmandthelowflowtripsetpointfrom95%to93%ofdesignRCSflow.ThisamendmentsupportedaSGTPlevelof30%+7%,witharequirementtoderateto90%of2700MWthpriortoexceeding7000EFPHofCycle14operation.TherequirementtoderatewasbasedontheSBLOCAanalysis,whichsupportedafullpoweroperationupto7000EFPHand90%powerlevelbeyond7000EFPH.ExceptfortheSBLOCA,acceptableresultswereshownwithintheapplicablesafetylimitsforallthesafetyandsetpointanalysesat100%poweroperationattheamendedconditionsandaSGTPlevelof30%+7%.TheSBLOCAwasevaluatedat100%ofratedpowerupto7000EFPHandat90%powerlevelbeyond7000EFPH.TosupportCycle14operationat2700MWthtoend-of-cyclerequiredareanalysisofSBLOCAwiththelimitingend-of-cycleconditions.TheSBLOCAhasbeenreanalyzedtosupportCycle14operationat100%powerfortheentireoperatingcycle.Theanalysis,includedastheenclosuretothisproposedlicenseamendment,demonstratesacceptableresultsincompliancewith10CFR50.46criteria.Thepeakcladdingtemperature(PCT)wascalculatedtobe1804'F,wellbelowtheacceptancecriteriaof2200'F.ThisanalysiswasperformedbySiemensPowerCorporation(SPC),usinganNRC-approvedSBLOCAevaluationmodel.Thereanalysiswasdonewithchangestoinputassumptionswithrespecttotheloopsealclearingandthelocationofcoldleginjectionpoint.Theloopsealsinthebrokenloopandoneoftheintactloopswerebiasedtoremainplugged.Inthecurrentanalysisofrecord,theloopsealinthebrokenloopdidnotstayplugged.Alsothesafetyinjectionpointwasmovedanodeawayfromthereactorcoolantpumptorepresentamorerealisticconfiguration.Overallthesechangesremovesomeoftheconservatismascomparedtotheanalysisofrecordfor25%tubeplugginglevel(EMF-92-148,"St.LucieUnit1SmallBreakLOCAAnalysis,"SiemensPowerCorporation,May1994).ConclusionTheSBLOCAreanalysis,alongwiththeanalysesaddressedinAmendmentNo.145,supportoperationofSt.LucieUnit1at100%ofRATEDTHERMALPOWERfortheentireCycle14.TheproposedchangesupportsthereducedRCSflowof345,000gpmcorrespondingtoaSGTPlevelof30%+7%approvedinAmendmentNo.145.

ATTACHMENT2DETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATION L-96-333Attachment2P~aeIDETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATIONDescriptionofamendmentrequest:TheproposedamendmentwilldeleteafootnoteassociatedwithTechnicalSpecification2.1.1,"ReactorCoreSafetyLimits,"whichrequiresthermalpowertobelimitedto90%of2700Megawattsthermal(MWth)forCycle14operationbeyond7000EffectiveFullPowerHours.Pursuantto10CFR50.92,adeterminationmaybemadethataproposedlicenseamendmentinvolvesnosignificanthazardsconsiderationifoperationofthefacilityinaccordancewiththeproposedamendmentwouldnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated;or(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated;or(3)involveasignificantreductioninamarginofsafety.Eachstandardisdiscussedasfollows:(1)OperationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasigniTicantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.TheproposedchangewillallowfullCycle14operationat100%ofratedpower(2700MWth),bydeletingtherequirementtoderateto90%ofratedpowerpriortoexceeding7000EFPH.ThisrestrictionwasimposedintheNRCtransmittalletterforLicenseAmendment145forSBLOCAconsiderationswhenconsideringtheincreasedSGTPlevelof30%+7%.AllFinalSafetyAnalysisReport(FSAR)events,otherthanSBLOCAwereevaluatedat100%ofratedthermalpowerandshowednosignificantincreasesintheprobabilityorconsequencesofaccidentspreviouslyevaluated.TheSBLOCAwasreanalyzedtodemonstratecontinuedcompliancewith10CFR50.46criteria.ThereisnoimpactoftheproposedchangeonanyFSARaccidentinitiator.Theplantconfigurationandsystemsremainunchanged.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.(2)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.ThisproposedamendmentremovestherequirementintheTechnicalSpecificationstoderateto90%of2700MWthforCycle14operationbeyond7000EFPH.Therewillbe L-96-333Attachment2P~ae2nochangetothemodesofoperationoftheplant.Theplantconfigurationandthedesignfunctionsofallthesafetysystemsremainunchanged.Theproposedamendmentwillnotchangethephysicalplantorthemodesofoperationdefinedinthefacilitylicense.Thechangesdonotinvolvetheadditionofnewequipmentorthemodificationofexistingequipment,nordotheyalterthedesignofSt.Lucieplantsystems.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifFerentkindofaccidentfromanyaccidentpreviouslyevaluated.(3)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.Theimpactoftheproposedchangeon'availablemargintotheacceptancecriteriaforSpecifiedAcceptableFuelDesignLimits(SAFDL),primaryandsecondaryover-pressurization,peakcontainmentpressure,potentialradioactivereleases,10CFR50.46requirementsforthelargebreakLOCA,andexistinglimitingconditionsforoperationhasbeenevaluatedandaddressedinthereducedRCSflowoperatinglicenseAmendmentNo.145.Arequirementtoderateto90%of2700MWthwasimposedbasedontheSBLOCAanalysis.ThesmallbreakLOCAanalysiswith30%+7%SGTPsupportedoperationupto7000EFPHat100%of-ratedthermalpower.AreanalysisofSBLOCAwiththelimitingend-of-cycleconditionsat100%ofratedpower,demonstratescontinuedcompliancewith10CFR50.46criteria.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.BasedonthediscussionpresentedaboveandonthesupportingEvaluationofProposedTS~Changes,FPLhasconcludedthatthisproposedlicenseamendmentinvolvesnosignificanthazardsconsideration.