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St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Page3STATEOFFLORIDA))COUNTYOFST.LUCIE)SS~D.A.Sagerbeingfirstdulysworn,deposesandsays:ThatheisVicePresident,St.LuciePlantfortheNuclearDivisionofFloridaPower6LightCompany,theLicenseeherein;Thathehasexecutedtheforegoingdocumentithatthestatementsmadeinthisdocumentaretrueandcorrecttothebestofhisknowledge,informationandbelief,andthatheisauthorizedtoexecutethedocumentonbehalfofsaidLicensee.D.A.SerSTATEOFFLORIDACOUNTYOFTheforegoinginstrumentwasacknowledgedbeforemethisIt~dayof,19'yD.A.Sager,whoispersonalyknowntomeandwhodidtakeanoath.NameofNotaryPublicMyCommissionexpiresSCommissionNo.2)Gal1S0~I'yOFFICIALNOTARySEALQy8~<)ALEXISRMOLENDA~COMMISSIONNIIMSSRCC156115yCOMMISSIONpXIsocT.ggqgg5 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsATTACHMENT1EVALUATIONOFPROPOSEDTSCHANGES 1cSt.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemerature.LimitsL-95-139Attachment1Page1of8EVALUATIONOFPROPOSEDTSCHANGESIntroductionFloridaPowerandLightCompany(FPL)proposestochangetheSt.LucieUnit1TechnicalSpecifications(TS)forReactorCoolantSystem(RCS)Pressure/TemperatureLimitsandmaximumallowedRCSheatupandcooldownrates.Theapplicabilityoftheexistingspecifiedlimitswillbeextendedfrom15EffectiveFullPowerYears(EFPY)to23.6EFPYofoperation.TheassociatedLowTemperatureOverpressureProtection(LTOP)requirementswilllikewisebeextended.Inaddition,administrativechangesareproposedforTS3.1.2.1andTS3.1.2.3toclarifytheconditionsrequiredifaHighPressureSafetyInjection(HPSI)pumpisusedtoestablishaborationflowpathduringoperationalModes5and6.DescritionofChanesMarked-upcopiesoftheaffectedTSpagesarecontainedinAttachment4.Adescriptionoftheproposedchangesfollows:1~TS3.4.9.1currentlyprovidesthepressureandtemperaturelimitsintermsofFigures3.4-2a,3.4-2b,and3.4-3fortheRCS(exceptthepressurizer)duringheatup,cooldown,criticality,andinserviceleakandhydrostatictestingfor15EFPY.Theproposedamendmentwouldusetheseexistingfigures,as-is,andonlyrevisethetitlebychanging"15EFPYttto>t236EFPY2~3~Footnote"*"isappendedtoTS3.1.2.1andTS3.1.2.3,applicableduringModes5and6,toproviderequirementsthatmustbemetiftheborationflowpathfromtheRefuelingWaterTank(RWT)isestablishedviaasingleHPSIpump.Thisfootnotewillberevisedtomoreclearlyindicatethatthespecifiedrequirementsapplytotheconditionwhennochargingpumpsareoperable.Figure3.1-lbspecifiesthemaximumallowableheatupandcooldownratesforthecasewhereasingleHPSIpumpisinoperationpursuanttoTS3.1.2.1andTS3.1.2.3.Thelimitofapplicabilityforthisfigurewillbeindicatedbyadding"23.6EFPY"tothetitle.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Page3STATEOFFLORIDA))COUNTYOFST.LUCIE)SS~D.A.Sagerbeingfirstdulysworn,deposesandsays:ThatheisVicePresident,St.LuciePlantfortheNuclearDivisionofFloridaPower6LightCompany,theLicenseeherein;Thathehasexecutedtheforegoingdocumentithatthestatementsmadeinthisdocumentaretrueandcorrecttothebestofhisknowledge,informationandbelief,andthatheisauthorizedtoexecutethedocumentonbehalfofsaidLicensee.D.A.SerSTATEOFFLORIDACOUNTYOFTheforegoinginstrumentwasacknowledgedbeforemethisIt~dayof,19'yD.A.Sager,whoispersonalyknowntomeandwhodidtakeanoath.NameofNotaryPublicMyCommissionexpiresSCommissionNo.2)Gal1S0~I'yOFFICIALNOTARySEALQy8~<)ALEXISRMOLENDA~COMMISSIONNIIMSSRCC156115yCOMMISSIONpXIsocT.ggqgg5 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsATTACHMENT1EVALUATIONOFPROPOSEDTSCHANGES 1cSt.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemerature.LimitsL-95-139Attachment1Page1of8EVALUATIONOFPROPOSEDTSCHANGESIntroductionFloridaPowerandLightCompany(FPL)proposestochangetheSt.LucieUnit1TechnicalSpecifications(TS)forReactorCoolantSystem(RCS)Pressure/TemperatureLimitsandmaximumallowedRCSheatupandcooldownrates.Theapplicabilityoftheexistingspecifiedlimitswillbeextendedfrom15EffectiveFullPowerYears(EFPY)to23.6EFPYofoperation.TheassociatedLowTemperatureOverpressureProtection(LTOP)requirementswilllikewisebeextended.Inaddition,administrativechangesareproposedforTS3.1.2.1andTS3.1.2.3toclarifytheconditionsrequiredifaHighPressureSafetyInjection(HPSI)pumpisusedtoestablishaborationflowpathduringoperationalModes5and6.DescritionofChanesMarked-upcopiesoftheaffectedTSpagesarecontainedinAttachment4.Adescriptionoftheproposedchangesfollows:1~TS3.4.9.1currentlyprovidesthepressureandtemperaturelimitsintermsofFigures3.4-2a,3.4-2b,and3.4-3fortheRCS(exceptthepressurizer)duringheatup,cooldown,criticality,andinserviceleakandhydrostatictestingfor15EFPY.Theproposedamendmentwouldusetheseexistingfigures,as-is,andonlyrevisethetitlebychanging"15EFPYttto>t236EFPY2~3~Footnote"*"isappendedtoTS3.1.2.1andTS3.1.2.3,applicableduringModes5and6,toproviderequirementsthatmustbemetiftheborationflowpathfromtheRefuelingWaterTank(RWT)isestablishedviaasingleHPSIpump.Thisfootnotewillberevisedtomoreclearlyindicatethatthespecifiedrequirementsapplytotheconditionwhennochargingpumpsareoperable.Figure3.1-lbspecifiesthemaximumallowableheatupandcooldownratesforthecasewhereasingleHPSIpumpisinoperationpursuanttoTS3.1.2.1andTS3.1.2.3.Thelimitofapplicabilityforthisfigurewillbeindicatedbyadding"23.6EFPY"tothetitle.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page2of8BackroundThereactorcoolantpressureboundaryisdesignedpursuantto10CFRPart50,AppendixA,DesignCriteria14and31.Thesedesigncriteriarequirethatthereactorcoolantpressureboundarybedesigned,fabricated,erectedandtestedinordertohaveanextremelylowprobabilityofabnormalleakage,ofrapidlypropagatingfailure,andofgrossrupture.Thecriteriaalsorequirethatthereactorcoolantpressureboundarybedesignedwithsufficientmargintoassurethat,whenstressed,theboundarybehavesinanon-brittlemanner,andthattheprobabilityofrapidlypropagatingfractureisminimized.Pressure/Temperature(P/T)limitsaredevelopedtoprovideadequatesafetymarginsforthepreventionoffractureoftheRCScoolantpressureboundarypursuantto10CFR50,AppendixG,"FractureToughnessRequirements."TheASMECodeformsthebasisfortheserequirements.ThemethodtopredictthereactorvesselmaterialirradiationdamageisprovidedinUSNRCRegulatoryGuide(RG)1.99,Rev.2,"RadiationEmbrittlementofReactorVesselMaterials".TheexistingP/Tlimitswereimplementedin1990,andarebasedonpredictionsforupto15EFPYofreactoroperation.ItisanticipatedthatPSL1willachieve15EFPYofoperationduringthespringof1996.FPLrecalculatedthepredictedmaterialradiationdamagebasedonrecent.dataobtainedinresponsetoNRCGenericLetter92OlgReactorVesselStructuralIntegrity."UsingthisnewdataandRG1.99,Rev.2,itwasdeterminedthattheexistingmaterialradiationdamagepredictioncanbeextendedto23.6EFPYofoperation.AdditionalassurancethatRCSP/TlimitswillnotbeexceededinthelowertemperatureoperatingmodesisprovidedbytheLowTemperatureOverpressureProtection(LTOP)system.Analysesforthissystemconsidertheinitiationofassumedenergy-additionandmass-additiontransientswhileoperatingatlowtemperaturesinaccordancewithStandardReviewPlan5.2.2,Revision2.BasesforProosedTSChanesTheanalysisfortheP/TlimitsandLTOPrequirementsfor15EFPYwereprovidedwithFPLletterL-89-408(Reference3),andsubsequentlyapprovedbytheissuanceofAmendmentNo.104(Reference1)tothefacilityoperatinglicense.Thebasisfordeterminingthattheselimitscanbeextendedto23.6EFPYisprovidedbelowbyreviewingtheconclusionsofeachsectionoftheanalysis.  
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page2of8BackroundThereactorcoolantpressureboundaryisdesignedpursuantto10CFRPart50,AppendixA,DesignCriteria14and31.Thesedesigncriteriarequirethatthereactorcoolantpressureboundarybedesigned,fabricated,erectedandtestedinordertohaveanextremelylowprobabilityofabnormalleakage,ofrapidlypropagatingfailure,andofgrossrupture.Thecriteriaalsorequirethatthereactorcoolantpressureboundarybedesignedwithsufficientmargintoassurethat,whenstressed,theboundarybehavesinanon-brittlemanner,andthattheprobabilityofrapidlypropagatingfractureisminimized.Pressure/Temperature(P/T)limitsaredevelopedtoprovideadequatesafetymarginsforthepreventionoffractureoftheRCScoolantpressureboundarypursuantto10CFR50,AppendixG,"FractureToughnessRequirements."TheASMECodeformsthebasisfortheserequirements.ThemethodtopredictthereactorvesselmaterialirradiationdamageisprovidedinUSNRCRegulatoryGuide(RG)1.99,Rev.2,"RadiationEmbrittlementofReactorVesselMaterials".TheexistingP/Tlimitswereimplementedin1990,andarebasedonpredictionsforupto15EFPYofreactoroperation.ItisanticipatedthatPSL1willachieve15EFPYofoperationduringthespringof1996.FPLrecalculatedthepredictedmaterialradiationdamagebasedonrecent.dataobtainedinresponsetoNRCGenericLetter92OlgReactorVesselStructuralIntegrity."UsingthisnewdataandRG1.99,Rev.2,itwasdeterminedthattheexistingmaterialradiationdamagepredictioncanbeextendedto23.6EFPYofoperation.AdditionalassurancethatRCSP/TlimitswillnotbeexceededinthelowertemperatureoperatingmodesisprovidedbytheLowTemperatureOverpressureProtection(LTOP)system.Analysesforthissystemconsidertheinitiationofassumedenergy-additionandmass-additiontransientswhileoperatingatlowtemperaturesinaccordancewithStandardReviewPlan5.2.2,Revision2.BasesforProosedTSChanesTheanalysisfortheP/TlimitsandLTOPrequirementsfor15EFPYwereprovidedwithFPLletterL-89-408(Reference3),andsubsequentlyapprovedbytheissuanceofAmendmentNo.104(Reference1)tothefacilityoperatinglicense.Thebasisfordeterminingthattheselimitscanbeextendedto23.6EFPYisprovidedbelowbyreviewingtheconclusionsofeachsectionoftheanalysis.  
'II St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page3of8EXTENDINGTHEAPPLICABILITYOFTHEP/TLIMITCURVESTheP/Tlimitcurveanalysisfor15EFPYwasdevelopedusingtherequirementsof10CFR50AppendixG.ThebasiccalculationmethodwasreferencedtoASMEBoilerandPressureVesselCode,SectionIII,AppendixG(1986).Thecurrentmethodisunchangedexceptthatin1992ASMErelocatedAppendixGtoSectionXI,andthereferencestressintensity,Km,isnowreferredtoasK.TheirradiatedmaterialpropertiesfortheP/TlimitcurvesarebasedupontheirradiationdamagepredictionmethodsofRG1.99,Rev.2,whichareusedtocalculatetheadjustedreferencetemperature(ART)forallreactorvesselbeltlinematerials.TheseARTpredictionsutilizeinitialmaterialtestproperties,materialchemistry,neutronfluenceandmargin,andistheprimarymaterialvariableinputthatisconsideredintheP/Tanalysis.AhigherARTvalueismorelimitingforplantoperation.TheARTisdeterminedforthereactorvessellimitingbeltlinematerialsfortheperiodofapplicabilityfortheP/Tlimitcurvesbasedonthepredictedneutronfluence.ThesevaluesareshowninthefirstportionofTable1(Attachment2ofthissubmittal).ThecontrollingvaluesofARTusedfortheP/TlimitcurvesandLTOPanalysisat15EFPYwere191Fatthe1/4Thickness(1/4T)locationand137'Fatthe3/4Thickness(3/4T)location(Ref.3,Attachment4,page9).Thecontrollingmaterialwasthelowershelllongitudinalwelds(3-203A,BandC,materialheatnumber305424)forthe1/4Tlocationandtwoofthelowershellplates(C 1andC 2)forthe3/4Tlocation.Theterm"controlling"meanshavingthehighestARTforagiventimeandpositionwithinthevesselwall.ThehighestART'sarethenusedtodeveloptheP/Tlimitsforthecorrespondingperiod.NotethatindevelopingtheP/Tlimits,aboundingmaterial(SA302GradeB)isassumed.
'II St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page3of8EXTENDINGTHEAPPLICABILITYOFTHEP/TLIMITCURVESTheP/Tlimitcurveanalysisfor15EFPYwasdevelopedusingtherequirementsof10CFR50AppendixG.ThebasiccalculationmethodwasreferencedtoASMEBoilerandPressureVesselCode,SectionIII,AppendixG(1986).Thecurrentmethodisunchangedexceptthatin1992ASMErelocatedAppendixGtoSectionXI,andthereferencestressintensity,Km,isnowreferredtoasK.TheirradiatedmaterialpropertiesfortheP/TlimitcurvesarebasedupontheirradiationdamagepredictionmethodsofRG1.99,Rev.2,whichareusedtocalculatetheadjustedreferencetemperature(ART)forallreactorvesselbeltlinematerials.TheseARTpredictionsutilizeinitialmaterialtestproperties,materialchemistry,neutronfluenceandmargin,andistheprimarymaterialvariableinputthatisconsideredintheP/Tanalysis.AhigherARTvalueismorelimitingforplantoperation.TheARTisdeterminedforthereactorvessellimitingbeltlinematerialsfortheperiodofapplicabilityfortheP/Tlimitcurvesbasedonthepredictedneutronfluence.ThesevaluesareshowninthefirstportionofTable1(Attachment2ofthissubmittal).ThecontrollingvaluesofARTusedfortheP/TlimitcurvesandLTOPanalysisat15EFPYwere191Fatthe1/4Thickness(1/4T)locationand137'Fatthe3/4Thickness(3/4T)location(Ref.3,Attachment4,page9).Thecontrollingmaterialwasthelowershelllongitudinalwelds(3-203A,BandC,materialheatnumber305424)forthe1/4Tlocationandtwoofthelowershellplates(C-8-1andC-8-2)forthe3/4Tlocation.Theterm"controlling"meanshavingthehighestARTforagiventimeandpositionwithinthevesselwall.ThehighestART'sarethenusedtodeveloptheP/Tlimitsforthecorrespondingperiod.NotethatindevelopingtheP/Tlimits,aboundingmaterial(SA302GradeB)isassumed.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page4of8RG1.99,Rev.2,predictionsforARTaredeterminedfromthefollowingformulas:ART=InitialRT~T+dZT~T+MarginInitialRTDTReferencetemperature('F)fortheun-irradiatedmaterial.MTgDyMargin(CF)f(0.28-0.10logQ"CF"('F)isthechemistryfactor,afunctionofCopperandNickelcontentoftheweldorbasematerial."f"isthecalculatedneutronfluence(10'/cm,E>1MeV)atthedepthintothevesselfromtheinsidediameterwettedsurfacetothepostulatedflaw(surface,1/4Tand3/4T).Projectionsoffluencearemadeforspecificperiodsoftimeofoperation(EFPY).ThethicknessT,withoutthecladding,isconservativelyusedtogiveahigherprojectedRT~DT.Thequantity('F)tobeaddedtoobtainaconservativeupperboundvalueofART.2(0~+0~)"0',=O'Fformeasuredtestvalues,17forgenericdatao'~=17'Fforplateand28'FforweldsNewbeltlineweldmaterialdatabecameavailableasaresultoftheresearchneededtorespondtoNRCGenericLetter92-01.ThisdataishighlightedinthesecondsectionofTable1.Asdescribedbelow,theplantspecificdatasignificantlyreducesthevaluesusedincalculatingtheART.Forthelimitinglowerlongitudinalwelds,thedataincludednewchemistryvaluesforcopperandnickel,andanactualinitialRTz,T.ThisnewdatacamefromtheDuquesneLightCo.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page4of8RG1.99,Rev.2,predictionsforARTaredeterminedfromthefollowingformulas:ART=InitialRT~T+dZT~T+MarginInitialRTDTReferencetemperature('F)fortheun-irradiatedmaterial.MTgDyMargin(CF)f(0.28-0.10logQ"CF"('F)isthechemistryfactor,afunctionofCopperandNickelcontentoftheweldorbasematerial."f"isthecalculatedneutronfluence(10'/cm,E>1MeV)atthedepthintothevesselfromtheinsidediameterwettedsurfacetothepostulatedflaw(surface,1/4Tand3/4T).Projectionsoffluencearemadeforspecificperiodsoftimeofoperation(EFPY).ThethicknessT,withoutthecladding,isconservativelyusedtogiveahigherprojectedRT~DT.Thequantity('F)tobeaddedtoobtainaconservativeupperboundvalueofART.2(0~+0~)"0',=O'Fformeasuredtestvalues,17forgenericdatao'~=17'Fforplateand28'FforweldsNewbeltlineweldmaterialdatabecameavailableasaresultoftheresearchneededtorespondtoNRCGenericLetter92-01.ThisdataishighlightedinthesecondsectionofTable1.Asdescribedbelow,theplantspecificdatasignificantlyreducesthevaluesusedincalculatingtheART.Forthelimitinglowerlongitudinalwelds,thedataincludednewchemistryvaluesforcopperandnickel,andanactualinitialRTz,T.ThisnewdatacamefromtheDuquesneLightCo.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page5of8BeaverValleyUnit1reactorvesselsurveillanceprogram(Ref.4),whichhasmaterialidenticaltotheSt.LucieUnit1lowerlongitudinalwelds.AsaresultofusingactualplantspecificRT>>Tdata,theoverallmargintermisreducedfrom65.5'Fto56'F,becausea,becomes0'F.TheinitialRT>>~isloweredfrom-56'Fto-60'F.ThenewchemistryvalueswereusedwithexistingSt.Lucie1qualificationdatatogetnewaveragecopperandnickelvalues(Ref.4),whichloweredthe'Fvaluefrom200.2to191.7.BasedonthesurveillancecapsuledataremovedfromtheSt.LucieUnit1reactorvessel,theCF'sforthelimitinglowershellplateswerecalculatedandprovidedtoFPLbytheNRC(Ref.5).ThenewCFvalueswerelowered,nominallyfrom108to80.SinceplantspecificdataisusedtocalculatetheCF,themarginterm(cr~)canbehalvedfrom34'Fto17'F(RG1.99,Rev.2,Position2.1).ThisdataishighlightedinthesecondsectionofTable1.Usingthenewdata,FPLcalculated(Ref.6)theneutronfluencethatwouldresultinvaluesofRTNDTequaltoorlessthanthelimitingARTsdeterminedinthe15EFPYanalysis.Thenewvaluesoffluencecorrespondto23.6EFPY,asshowninthethirdsectionofTable1.Notethatthelowerlongitudinalweldsarenowthecontrollingmaterialatboththe1/4Tand3/4Tlocations.Sincethe23.6EFPYlimitingRT>>~valueswereequaltoorlessthanthoseusedinthe15EFPYanalysis,thecurrentTechnicalSpecificationP/TlimitcurvesandLTOPanalysiswouldbeapplicableforaperiodnottoexceed23.6EFPYwiththesamemarginofsafetyastheprevious15EFPYanalysis.ThisequivalencecoverstheP/Tlimitsforheatup,cooldown,hydrostatictestandcorecriticaloperation.2~LOWESTSERVICETEMPERATURE,MINIMUMBOLTUPTEMPERATURE,ANDMINIMUMPRESSURELIMITSTheP/Tanalysisfor15EFPYcalculatedthelimitsforlowestservicetemperature,minimumboltuptemperature,andminimumpressurelimitsforreference.Theselimitsarenotbasedonaccumulatedfluenceatthereactorvesselbeltlinematerial,andremainunchanged.ThelowestservicetemperatureisbasedonthemostlimitingRT>>TforthebalanceofRCScomponents,whichistheReactorCoolantPump(RCP).Accumulatedplantoperationdoesnoteffectthiscomponent'smaterialproperties,thereforethelowestservicetemperatureremainsthesame.  
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page5of8BeaverValleyUnit1reactorvesselsurveillanceprogram(Ref.4),whichhasmaterialidenticaltotheSt.LucieUnit1lowerlongitudinalwelds.AsaresultofusingactualplantspecificRT>>Tdata,theoverallmargintermisreducedfrom65.5'Fto56'F,becausea,becomes0'F.TheinitialRT>>~isloweredfrom-56'Fto-60'F.ThenewchemistryvalueswereusedwithexistingSt.Lucie1qualificationdatatogetnewaveragecopperandnickelvalues(Ref.4),whichloweredthe'Fvaluefrom200.2to191.7.BasedonthesurveillancecapsuledataremovedfromtheSt.LucieUnit1reactorvessel,theCF'sforthelimitinglowershellplateswerecalculatedandprovidedtoFPLbytheNRC(Ref.5).ThenewCFvalueswerelowered,nominallyfrom108to80.SinceplantspecificdataisusedtocalculatetheCF,themarginterm(cr~)canbehalvedfrom34'Fto17'F(RG1.99,Rev.2,Position2.1).ThisdataishighlightedinthesecondsectionofTable1.Usingthenewdata,FPLcalculated(Ref.6)theneutronfluencethatwouldresultinvaluesofRTNDTequaltoorlessthanthelimitingARTsdeterminedinthe15EFPYanalysis.Thenewvaluesoffluencecorrespondto23.6EFPY,asshowninthethirdsectionofTable1.Notethatthelowerlongitudinalweldsarenowthecontrollingmaterialatboththe1/4Tand3/4Tlocations.Sincethe23.6EFPYlimitingRT>>~valueswereequaltoorlessthanthoseusedinthe15EFPYanalysis,thecurrentTechnicalSpecificationP/TlimitcurvesandLTOPanalysiswouldbeapplicableforaperiodnottoexceed23.6EFPYwiththesamemarginofsafetyastheprevious15EFPYanalysis.ThisequivalencecoverstheP/Tlimitsforheatup,cooldown,hydrostatictestandcorecriticaloperation.2~LOWESTSERVICETEMPERATURE,MINIMUMBOLTUPTEMPERATURE,ANDMINIMUMPRESSURELIMITSTheP/Tanalysisfor15EFPYcalculatedthelimitsforlowestservicetemperature,minimumboltuptemperature,andminimumpressurelimitsforreference.Theselimitsarenotbasedonaccumulatedfluenceatthereactorvesselbeltlinematerial,andremainunchanged.ThelowestservicetemperatureisbasedonthemostlimitingRT>>TforthebalanceofRCScomponents,whichistheReactorCoolantPump(RCP).Accumulatedplantoperationdoesnoteffectthiscomponent'smaterialproperties,thereforethelowestservicetemperatureremainsthesame.  
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==REFERENCES:==
==REFERENCES:==
1~2~3~4~5.6.7~8.9.USNRClettertoJ.H.Goldberg,"St.LucieUnit1-IssuanceofAmendmentRe:PressureTemperature(P/T)LimitsandLowTemperatureOverpressureProtection(LTOP)Analysis(TACNo.75386)",datedJunell,1990.(Amendment104)(Notused)FPLlettertoUSNRC,L-89-408,"St.LucieUnit1,DocketNo.50-335,ProposedLicenseAmendment,P-TLimitsandLTOPAnalysis",datedDecember5,1989.FPLlettertoUSNRC,L-93-286,"St.LucieUnit1and2,DocketNo.50-335and50-389,GenericLetter92-01,Revision1,ResponsetoRequestforAdditionalInformation(RAI)",datedNovember15,1993.USNRCLettertoJ.H.Goldberg;GenericLetter(GL)92-01,Revision1,"ReactorVesselStructuralIntegrity,"St.LucieUnit1and2(TACNOSM83505andM83506);May26,1994.FPLcalculationPSL-lFJM-95-004,Rev.0,"St.LucieUnit1ReactorVesselAdjustedReferenceTemperatureandLTOPlimitsat23.6EFPY",dated3/22/95.USNRCGenericLetter92-01"ReactorVesselStructuralIntegrity",Revision1,DatedMarch6,1992.USNRCInformationNotice93-58"Non-conservatisminLow-TemperatureOverpressureProtectionforPressurizedWaterReactors",datedJuly26,1993.CEReportTR-F-MCM-004"FPL,PSL-1EvaluationofIrradiatedCapsuleW97",datedDecember,1983.
1~2~3~4~5.6.7~8.9.USNRClettertoJ.H.Goldberg,"St.LucieUnit1-IssuanceofAmendmentRe:PressureTemperature(P/T)LimitsandLowTemperatureOverpressureProtection(LTOP)Analysis(TACNo.75386)",datedJunell,1990.(Amendment104)(Notused)FPLlettertoUSNRC,L-89-408,"St.LucieUnit1,DocketNo.50-335,ProposedLicenseAmendment,P-TLimitsandLTOPAnalysis",datedDecember5,1989.FPLlettertoUSNRC,L-93-286,"St.LucieUnit1and2,DocketNo.50-335and50-389,GenericLetter92-01,Revision1,ResponsetoRequestforAdditionalInformation(RAI)",datedNovember15,1993.USNRCLettertoJ.H.Goldberg;GenericLetter(GL)92-01,Revision1,"ReactorVesselStructuralIntegrity,"St.LucieUnit1and2(TACNOSM83505andM83506);May26,1994.FPLcalculationPSL-lFJM-95-004,Rev.0,"St.LucieUnit1ReactorVesselAdjustedReferenceTemperatureandLTOPlimitsat23.6EFPY",dated3/22/95.USNRCGenericLetter92-01"ReactorVesselStructuralIntegrity",Revision1,DatedMarch6,1992.USNRCInformationNotice93-58"Non-conservatisminLow-TemperatureOverpressureProtectionforPressurizedWaterReactors",datedJuly26,1993.CEReportTR-F-MCM-004"FPL,PSL-1EvaluationofIrradiatedCapsuleW97",datedDecember,1983.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsATTACHMENT2TABLE1ST~LUCIEUNIT1REACTORVESSELBELTLINEADJUSTEDREFERENCETEMPERATURESFORDETERMININGPRESSURETEMPERATUREANDLTOPLIMITSCURVES TABLE1:STLUCIEUNIT1REACTORVESSELBELTLINEADJUSTEDREFERENCETEMPERATURESFORDETERMININGPRESSURETEMPERATUREANDLTOPLIMITSCURVES15YEARPT/LTOPCURVESUSINGEXISTING1989ANALYSIS(Originalcriticalvaluesbolded)LOCATIONID&#xb9;Cu%Ni%CALC.CFTABLECFINITIALRTndtMARGIN15EFPYPEAKFLUENCE,E19n/cm21/4TFLUENCE15YEARART15YEAR3/4TFLUENCE91/4TART93/4TLowershellsteLowershellsteInttoLowerirthweldsC 1C 2901360.150.150.230.560.570.11107.8108.4109.820OF20oF-60oF34OF34oF56oF2.05E+192.05E+192.05E+191.22E+191.22E+191.22E+194.34E+18168oF4.34E+181BBOF4.34E+18112OF137oF137OF80OFLowerlongitudinalwelds3054240.30O.B4200.2-56oF65.5oF1.202E+197.16E+182.54E+18191F135oFNEWCHEMISTRYFACTORS5MARGINSBASEDONGL92-01VALUES(ChangesresultingfromnewdatasubmittedwithGL92-01anduseofcapsuledataforplatesbolded)LOCATIONID&#xb9;CU%CALC.CFTABLECFINITIALRTndtMARGINLowershellsteLowershellsteInttoLowerirthweldsLowerlongitudinalweldsC 1C 2901383054240.150.150.230.28o.se79.42o.s779.82o.1184.800.63191.720oF20oF-60oF60oF17oF17oF28oF56oFEQUIVALENTFLUENCE(23.6EFPY)ATTIMEOFREACHINGRT/NDTVALUESUSEDIN1SEFPYCURVESWITHGL92%1CHEMISTRYFACTORS/MARGINS(Ref.7.6)(Newcriticalvaluesbolded)LOCATIONLowershelllateLowershellIsteInttoLowerirthweldsLowerlongitudinalweldsID&#xb9;C 1C 29013B305424Cu%0.150.150.230.28Ni%0.5B0.570.110.63CALC.CFTABLECF79.4279.8284.80191.7INITIALRTndt20OF20oF60oF60oFMARGIN17oF17OF28OF56oF22KBEFPYPEAKFLUENCE,E18n/cm22.82E+192.82E+192.82E+191.783E+191/4TFLUENCE3/4TFLUENCE1.BBE+195.97E+181.68E+195.97E+181.68E+195.97E+181.063E+193.78E+1823.BEFPYART61/4T128oF128oF65oF191oF23.6EFPYART93/4T105OF105OF41OF136oF St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsATTACHMENT3DETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATION St.LucieUnit,1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment3Page1of2DETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATIONPursuantto10CFR50.92,adeterminationmaybemadethataproposedlicenseamendmentinvolvesnosignificanthazardsconsiderationifoperationofthefacilityinaccordancewiththeproposedamendmentwouldnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated;or(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated;or(3)involveasignificantreductioninamarginofsafety.Eachstandardisdiscussedasfollows:(1)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.Thepressure-temperature(P/T)limitcurvesintheTechnicalSpecificationsareconservativelygeneratedinaccordancewiththefracturetoughnessrequirementsof10CFR50AppendixGassupplementedbytheASMECodeSectionXI,AppendixGrecommendations.TheRT>>~valuesarebasedonRegulatoryGuide1.99,Revision2,shiftpredictionandattenuationformula.AnalysesofreactorvesselmaterialirradiationsurveillancespecimensareusedtoverifythevalidityofthefluencepredictionsandtheP/Tlimitcurves.Useofthesecurvesinconjunctionwiththesurveillancespecimenprogramensuresthatthereactorcoolantpressureboundarywillbehaveinanon-brittlemannerandthatthepossibilityofrapidlypropagatingfractureisminimized.Basedontheuseofplantspecificmaterialdata,analysishasdemonstratedthatthecurrentP/Tlimitcurveswillremainconservativeforupto23.6EFPY.InconjunctionwithextendingtheapplicabilityoftheexistingP/Tlimitcurves,thelowtemperatureoverpressureprotection(LTOP)analysisfor15EFPYisalsoextended.TheLTOPanalysisconfirmsthatthecurrentsetpointsforthepower-operatedreliefvalves(PORVs)willprovidetheappropriateoverpressureprotectionatlowReactorCoolantSystem(RCS)temperatures.BecausetheP/Tlimitcurveshavenotchanged,theexistingLTOPvalueshavenotchanged,whichincludethePORVsetpoints,heatupandcooldownrates,anddisablingofnon-essentialcomponents.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsATTACHMENT2TABLE1ST~LUCIEUNIT1REACTORVESSELBELTLINEADJUSTEDREFERENCETEMPERATURESFORDETERMININGPRESSURETEMPERATUREANDLTOPLIMITSCURVES TABLE1:STLUCIEUNIT1REACTORVESSELBELTLINEADJUSTEDREFERENCETEMPERATURESFORDETERMININGPRESSURETEMPERATUREANDLTOPLIMITSCURVES15YEARPT/LTOPCURVESUSINGEXISTING1989ANALYSIS(Originalcriticalvaluesbolded)LOCATIONID&#xb9;Cu%Ni%CALC.CFTABLECFINITIALRTndtMARGIN15EFPYPEAKFLUENCE,E19n/cm21/4TFLUENCE15YEARART15YEAR3/4TFLUENCE91/4TART93/4TLowershellsteLowershellsteInttoLowerirthweldsC-8-1C-8-2901360.150.150.230.560.570.11107.8108.4109.820OF20oF-60oF34OF34oF56oF2.05E+192.05E+192.05E+191.22E+191.22E+191.22E+194.34E+18168oF4.34E+181BBOF4.34E+18112OF137oF137OF80OFLowerlongitudinalwelds3054240.30O.B4200.2-56oF65.5oF1.202E+197.16E+182.54E+18191F135oFNEWCHEMISTRYFACTORS5MARGINSBASEDONGL92-01VALUES(ChangesresultingfromnewdatasubmittedwithGL92-01anduseofcapsuledataforplatesbolded)LOCATIONID&#xb9;CU%CALC.CFTABLECFINITIALRTndtMARGINLowershellsteLowershellsteInttoLowerirthweldsLowerlongitudinalweldsC-8-1C-8-2901383054240.150.150.230.28o.se79.42o.s779.82o.1184.800.63191.720oF20oF-60oF60oF17oF17oF28oF56oFEQUIVALENTFLUENCE(23.6EFPY)ATTIMEOFREACHINGRT/NDTVALUESUSEDIN1SEFPYCURVESWITHGL92%1CHEMISTRYFACTORS/MARGINS(Ref.7.6)(Newcriticalvaluesbolded)LOCATIONLowershelllateLowershellIsteInttoLowerirthweldsLowerlongitudinalweldsID&#xb9;C-8-1C-8-29013B305424Cu%0.150.150.230.28Ni%0.5B0.570.110.63CALC.CFTABLECF79.4279.8284.80191.7INITIALRTndt20OF20oF60oF60oFMARGIN17oF17OF28OF56oF22KBEFPYPEAKFLUENCE,E18n/cm22.82E+192.82E+192.82E+191.783E+191/4TFLUENCE3/4TFLUENCE1.BBE+195.97E+181.68E+195.97E+181.68E+195.97E+181.063E+193.78E+1823.BEFPYART61/4T128oF128oF65oF191oF23.6EFPYART93/4T105OF105OF41OF136oF St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsATTACHMENT3DETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATION St.LucieUnit,1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment3Page1of2DETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATIONPursuantto10CFR50.92,adeterminationmaybemadethataproposedlicenseamendmentinvolvesnosignificanthazardsconsiderationifoperationofthefacilityinaccordancewiththeproposedamendmentwouldnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated;or(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated;or(3)involveasignificantreductioninamarginofsafety.Eachstandardisdiscussedasfollows:(1)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.Thepressure-temperature(P/T)limitcurvesintheTechnicalSpecificationsareconservativelygeneratedinaccordancewiththefracturetoughnessrequirementsof10CFR50AppendixGassupplementedbytheASMECodeSectionXI,AppendixGrecommendations.TheRT>>~valuesarebasedonRegulatoryGuide1.99,Revision2,shiftpredictionandattenuationformula.AnalysesofreactorvesselmaterialirradiationsurveillancespecimensareusedtoverifythevalidityofthefluencepredictionsandtheP/Tlimitcurves.Useofthesecurvesinconjunctionwiththesurveillancespecimenprogramensuresthatthereactorcoolantpressureboundarywillbehaveinanon-brittlemannerandthatthepossibilityofrapidlypropagatingfractureisminimized.Basedontheuseofplantspecificmaterialdata,analysishasdemonstratedthatthecurrentP/Tlimitcurveswillremainconservativeforupto23.6EFPY.InconjunctionwithextendingtheapplicabilityoftheexistingP/Tlimitcurves,thelowtemperatureoverpressureprotection(LTOP)analysisfor15EFPYisalsoextended.TheLTOPanalysisconfirmsthatthecurrentsetpointsforthepower-operatedreliefvalves(PORVs)willprovidetheappropriateoverpressureprotectionatlowReactorCoolantSystem(RCS)temperatures.BecausetheP/Tlimitcurveshavenotchanged,theexistingLTOPvalueshavenotchanged,whichincludethePORVsetpoints,heatupandcooldownrates,anddisablingofnon-essentialcomponents.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment3Page2of2Theproposedamendmentdoesnotchangetheconfigurationoroperationoftheplant,andassuranceisprovidedthatreactorvesselintegritywillbemaintained.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwillnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.(2)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Byapplyingplantspecificdatainthedeterminationofcriticalvesselmateriallimits,theapplicabilityoftheexistingpressuretemperaturelimitsandLTOPrequirementscanbeextended.Thereisnochangeintheconfigurationoroperationofthefacilityasaresultoftheproposedamendment.Theamendmentdoesnotinvolvetheadditionofnewequipmentorthemodificationofexistingequipment,nordoesitalterthedesignofSt.Lucieplantsystems.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.(3)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.Analysishasdemonstratedthatthefracturetoughnessrequirementsof10CFR50AppendixGaresatisfiedandthatconservativeoperatingrestrictionsaremaintainedforthepurposeoflowtemperatureoverpressureprotection.TheP/TlimitcurveswillprovideassurancethattheRCSpressureboundarywillbehaveinaductilemannerandthattheprobabilityofarapidlypropagatingfractureisminimized.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.BasedonthediscussionpresentedaboveandonthesupportingEvaluationofProposedTSChanges,FPLhasconcludedthatthisproposedlicenseamendmentinvolvesnosignificanthazardsconsideration.  
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment3Page2of2Theproposedamendmentdoesnotchangetheconfigurationoroperationoftheplant,andassuranceisprovidedthatreactorvesselintegritywillbemaintained.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwillnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.(2)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Byapplyingplantspecificdatainthedeterminationofcriticalvesselmateriallimits,theapplicabilityoftheexistingpressuretemperaturelimitsandLTOPrequirementscanbeextended.Thereisnochangeintheconfigurationoroperationofthefacilityasaresultoftheproposedamendment.Theamendmentdoesnotinvolvetheadditionofnewequipmentorthemodificationofexistingequipment,nordoesitalterthedesignofSt.Lucieplantsystems.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.(3)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.Analysishasdemonstratedthatthefracturetoughnessrequirementsof10CFR50AppendixGaresatisfiedandthatconservativeoperatingrestrictionsaremaintainedforthepurposeoflowtemperatureoverpressureprotection.TheP/TlimitcurveswillprovideassurancethattheRCSpressureboundarywillbehaveinaductilemannerandthattheprobabilityofarapidlypropagatingfractureisminimized.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.BasedonthediscussionpresentedaboveandonthesupportingEvaluationofProposedTSChanges,FPLhasconcludedthatthisproposedlicenseamendmentinvolvesnosignificanthazardsconsideration.  
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Revision as of 02:55, 2 May 2018

Application for Amend to License DPR-67,extending Applicability of Current RCS Pressure/Temp Limits & Maximum Allowed RCS Heatup & Cooldown Rates to 23.6 Effective Full Power Yrs of Operation
ML17228B145
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 05/17/1995
From: SAGER D A
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17228B146 List:
References
L-95-139, NUDOCS 9505240223
Download: ML17228B145 (21)
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Text

PRIDRITY1CCELERATEDRIDSPROCESSIVEG)REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9505240223DOC.DATE:95/05/17NOTARIZED:NOFACXL:50-335St.LuciePlant,Unit1,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIATIONSAGER,D.A.FloridaPower&LightCo.RECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)DOCKET05000335

SUBJECT:

ApplicationforamendtolicenseDPR-67,extendingapplicabilityofcurrentRCSpressure/templimits&maximumallowedRCSheatup&cooldownratesto23.6EffectiveFullPowerYRsofoperation.DISTRIBUTIONCODE:AOOIDCOPIESRECEIVED:LTR/ENCL/SIZE:TITLE:ORSubmittal:GeneralDistributionNOTES:RECIPIENTXDCODE/NAMEPD2-1LANORRIS,JINTERNAL:ACRSNRR/DE/EMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTEXTERNAL:NOACCOPIESLTTRENCL11116611111111RECXPIENTIDCODE/NAMEPD2-1PDFILECENTER01B'NRR/DSSA/SRXBOGC/HDS3NRCPDRCOPIESLTTRENCL111111111011NOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEiVKSTE!CONTAC'II'IIEDOCL'ifENTCONTROLDESk,ROOAfPl-37(EAT.504-0033)TOELIXIINKTEYOL'RNAifL'ROifDISTRIBUTIONLIS'I'SI'ORDOCLMEN'I'SYOL'ON"I'lI'.D!TOTALNUMBEROFCOPIESREQUIRED:LTTR.18ENCL17 FloridaPower&LightCompany,P.O.Box128,FortPierce,FL34954-0128May17,1995L-95-13910CFR50.90U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Re:St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsPursuantto10CFR50.90,FloridaPower&LightCompany(FPL)requeststoamendFacilityOperatingLicenseDPR-67forSt.LucieUnit1byincorporatingtheattachedTechnicalSpecifications(TS)revisions.TheamendmentwillextendtheapplicabilityofthecurrentReactorCoolantSystem(RCS)Pressure/TemperatureLimitsandmaximumallowedRCSheatupandcooldownratesto23.6EffectiveFullPowerYearsofoperation.Inaddition,administrativechangesareproposedforTS3.1.2.1(BorationSystemsFlowPaths-Shutdown)andTS3.1.2.3(ChargingPump-Shutdown)toclarifytheconditionsforwhichaHighPressureSafetyInjectionpumpmaybeused.Itisrequestedthattheproposedamendment,ifapproved,beissuedbyMarch31,1996.Attachment1isanevaluationoftheproposedTSchanges.Attachment2isatableofSt.LucieUnit1ReactorVesselBeltlineAdjustedReferenceTemperaturesforDeterminingPressureTemperatureandLTOPLimitsCurves.Attachment3isthe"DeterminationofNoSignificantHazardsConsideration."Attachment4containsacopyoftheappropriateTSpagesmarked-uptoshowtheproposedchanges.TheproposedamendmenthasbeenreviewedbytheSt.LucieFacilityReviewGroupandtheFloridaPower&LightCompanyNuclearReviewBoard.Inaccordancewith10CFR50.91(b)(1),acopyoftheproposedamendmentisbeingforwardedtotheStateDesigneefortheStateofFlorida.Pleasecontactusifthereareanyquestionsaboutthissubmittal.Verytrulyyours,D.A.aerVicePidentSt.LucePlantanFPLGroupcompany Ig~4 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Page2DAS/RLDAttachmentscc:StewartD.Ebneter,RegionalAdministrator,RegionII,USNRC.SeniorResidentInspector,USNRC,St.LuciePlant.Mr.W.A.Passetti,FloridaDepartmentofHealthandRehabilitativeServices.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Page3STATEOFFLORIDA))COUNTYOFST.LUCIE)SS~D.A.Sagerbeingfirstdulysworn,deposesandsays:ThatheisVicePresident,St.LuciePlantfortheNuclearDivisionofFloridaPower6LightCompany,theLicenseeherein;Thathehasexecutedtheforegoingdocumentithatthestatementsmadeinthisdocumentaretrueandcorrecttothebestofhisknowledge,informationandbelief,andthatheisauthorizedtoexecutethedocumentonbehalfofsaidLicensee.D.A.SerSTATEOFFLORIDACOUNTYOFTheforegoinginstrumentwasacknowledgedbeforemethisIt~dayof,19'yD.A.Sager,whoispersonalyknowntomeandwhodidtakeanoath.NameofNotaryPublicMyCommissionexpiresSCommissionNo.2)Gal1S0~I'yOFFICIALNOTARySEALQy8~<)ALEXISRMOLENDA~COMMISSIONNIIMSSRCC156115yCOMMISSIONpXIsocT.ggqgg5 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsATTACHMENT1EVALUATIONOFPROPOSEDTSCHANGES 1cSt.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemerature.LimitsL-95-139Attachment1Page1of8EVALUATIONOFPROPOSEDTSCHANGESIntroductionFloridaPowerandLightCompany(FPL)proposestochangetheSt.LucieUnit1TechnicalSpecifications(TS)forReactorCoolantSystem(RCS)Pressure/TemperatureLimitsandmaximumallowedRCSheatupandcooldownrates.Theapplicabilityoftheexistingspecifiedlimitswillbeextendedfrom15EffectiveFullPowerYears(EFPY)to23.6EFPYofoperation.TheassociatedLowTemperatureOverpressureProtection(LTOP)requirementswilllikewisebeextended.Inaddition,administrativechangesareproposedforTS3.1.2.1andTS3.1.2.3toclarifytheconditionsrequiredifaHighPressureSafetyInjection(HPSI)pumpisusedtoestablishaborationflowpathduringoperationalModes5and6.DescritionofChanesMarked-upcopiesoftheaffectedTSpagesarecontainedinAttachment4.Adescriptionoftheproposedchangesfollows:1~TS3.4.9.1currentlyprovidesthepressureandtemperaturelimitsintermsofFigures3.4-2a,3.4-2b,and3.4-3fortheRCS(exceptthepressurizer)duringheatup,cooldown,criticality,andinserviceleakandhydrostatictestingfor15EFPY.Theproposedamendmentwouldusetheseexistingfigures,as-is,andonlyrevisethetitlebychanging"15EFPYttto>t236EFPY2~3~Footnote"*"isappendedtoTS3.1.2.1andTS3.1.2.3,applicableduringModes5and6,toproviderequirementsthatmustbemetiftheborationflowpathfromtheRefuelingWaterTank(RWT)isestablishedviaasingleHPSIpump.Thisfootnotewillberevisedtomoreclearlyindicatethatthespecifiedrequirementsapplytotheconditionwhennochargingpumpsareoperable.Figure3.1-lbspecifiesthemaximumallowableheatupandcooldownratesforthecasewhereasingleHPSIpumpisinoperationpursuanttoTS3.1.2.1andTS3.1.2.3.Thelimitofapplicabilityforthisfigurewillbeindicatedbyadding"23.6EFPY"tothetitle.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page2of8BackroundThereactorcoolantpressureboundaryisdesignedpursuantto10CFRPart50,AppendixA,DesignCriteria14and31.Thesedesigncriteriarequirethatthereactorcoolantpressureboundarybedesigned,fabricated,erectedandtestedinordertohaveanextremelylowprobabilityofabnormalleakage,ofrapidlypropagatingfailure,andofgrossrupture.Thecriteriaalsorequirethatthereactorcoolantpressureboundarybedesignedwithsufficientmargintoassurethat,whenstressed,theboundarybehavesinanon-brittlemanner,andthattheprobabilityofrapidlypropagatingfractureisminimized.Pressure/Temperature(P/T)limitsaredevelopedtoprovideadequatesafetymarginsforthepreventionoffractureoftheRCScoolantpressureboundarypursuantto10CFR50,AppendixG,"FractureToughnessRequirements."TheASMECodeformsthebasisfortheserequirements.ThemethodtopredictthereactorvesselmaterialirradiationdamageisprovidedinUSNRCRegulatoryGuide(RG)1.99,Rev.2,"RadiationEmbrittlementofReactorVesselMaterials".TheexistingP/Tlimitswereimplementedin1990,andarebasedonpredictionsforupto15EFPYofreactoroperation.ItisanticipatedthatPSL1willachieve15EFPYofoperationduringthespringof1996.FPLrecalculatedthepredictedmaterialradiationdamagebasedonrecent.dataobtainedinresponsetoNRCGenericLetter92OlgReactorVesselStructuralIntegrity."UsingthisnewdataandRG1.99,Rev.2,itwasdeterminedthattheexistingmaterialradiationdamagepredictioncanbeextendedto23.6EFPYofoperation.AdditionalassurancethatRCSP/TlimitswillnotbeexceededinthelowertemperatureoperatingmodesisprovidedbytheLowTemperatureOverpressureProtection(LTOP)system.Analysesforthissystemconsidertheinitiationofassumedenergy-additionandmass-additiontransientswhileoperatingatlowtemperaturesinaccordancewithStandardReviewPlan5.2.2,Revision2.BasesforProosedTSChanesTheanalysisfortheP/TlimitsandLTOPrequirementsfor15EFPYwereprovidedwithFPLletterL-89-408(Reference3),andsubsequentlyapprovedbytheissuanceofAmendmentNo.104(Reference1)tothefacilityoperatinglicense.Thebasisfordeterminingthattheselimitscanbeextendedto23.6EFPYisprovidedbelowbyreviewingtheconclusionsofeachsectionoftheanalysis.

'II St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page3of8EXTENDINGTHEAPPLICABILITYOFTHEP/TLIMITCURVESTheP/Tlimitcurveanalysisfor15EFPYwasdevelopedusingtherequirementsof10CFR50AppendixG.ThebasiccalculationmethodwasreferencedtoASMEBoilerandPressureVesselCode,SectionIII,AppendixG(1986).Thecurrentmethodisunchangedexceptthatin1992ASMErelocatedAppendixGtoSectionXI,andthereferencestressintensity,Km,isnowreferredtoasK.TheirradiatedmaterialpropertiesfortheP/TlimitcurvesarebasedupontheirradiationdamagepredictionmethodsofRG1.99,Rev.2,whichareusedtocalculatetheadjustedreferencetemperature(ART)forallreactorvesselbeltlinematerials.TheseARTpredictionsutilizeinitialmaterialtestproperties,materialchemistry,neutronfluenceandmargin,andistheprimarymaterialvariableinputthatisconsideredintheP/Tanalysis.AhigherARTvalueismorelimitingforplantoperation.TheARTisdeterminedforthereactorvessellimitingbeltlinematerialsfortheperiodofapplicabilityfortheP/Tlimitcurvesbasedonthepredictedneutronfluence.ThesevaluesareshowninthefirstportionofTable1(Attachment2ofthissubmittal).ThecontrollingvaluesofARTusedfortheP/TlimitcurvesandLTOPanalysisat15EFPYwere191Fatthe1/4Thickness(1/4T)locationand137'Fatthe3/4Thickness(3/4T)location(Ref.3,Attachment4,page9).Thecontrollingmaterialwasthelowershelllongitudinalwelds(3-203A,BandC,materialheatnumber305424)forthe1/4Tlocationandtwoofthelowershellplates(C-8-1andC-8-2)forthe3/4Tlocation.Theterm"controlling"meanshavingthehighestARTforagiventimeandpositionwithinthevesselwall.ThehighestART'sarethenusedtodeveloptheP/Tlimitsforthecorrespondingperiod.NotethatindevelopingtheP/Tlimits,aboundingmaterial(SA302GradeB)isassumed.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page4of8RG1.99,Rev.2,predictionsforARTaredeterminedfromthefollowingformulas:ART=InitialRT~T+dZT~T+MarginInitialRTDTReferencetemperature('F)fortheun-irradiatedmaterial.MTgDyMargin(CF)f(0.28-0.10logQ"CF"('F)isthechemistryfactor,afunctionofCopperandNickelcontentoftheweldorbasematerial."f"isthecalculatedneutronfluence(10'/cm,E>1MeV)atthedepthintothevesselfromtheinsidediameterwettedsurfacetothepostulatedflaw(surface,1/4Tand3/4T).Projectionsoffluencearemadeforspecificperiodsoftimeofoperation(EFPY).ThethicknessT,withoutthecladding,isconservativelyusedtogiveahigherprojectedRT~DT.Thequantity('F)tobeaddedtoobtainaconservativeupperboundvalueofART.2(0~+0~)"0',=O'Fformeasuredtestvalues,17forgenericdatao'~=17'Fforplateand28'FforweldsNewbeltlineweldmaterialdatabecameavailableasaresultoftheresearchneededtorespondtoNRCGenericLetter92-01.ThisdataishighlightedinthesecondsectionofTable1.Asdescribedbelow,theplantspecificdatasignificantlyreducesthevaluesusedincalculatingtheART.Forthelimitinglowerlongitudinalwelds,thedataincludednewchemistryvaluesforcopperandnickel,andanactualinitialRTz,T.ThisnewdatacamefromtheDuquesneLightCo.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page5of8BeaverValleyUnit1reactorvesselsurveillanceprogram(Ref.4),whichhasmaterialidenticaltotheSt.LucieUnit1lowerlongitudinalwelds.AsaresultofusingactualplantspecificRT>>Tdata,theoverallmargintermisreducedfrom65.5'Fto56'F,becausea,becomes0'F.TheinitialRT>>~isloweredfrom-56'Fto-60'F.ThenewchemistryvalueswereusedwithexistingSt.Lucie1qualificationdatatogetnewaveragecopperandnickelvalues(Ref.4),whichloweredthe'Fvaluefrom200.2to191.7.BasedonthesurveillancecapsuledataremovedfromtheSt.LucieUnit1reactorvessel,theCF'sforthelimitinglowershellplateswerecalculatedandprovidedtoFPLbytheNRC(Ref.5).ThenewCFvalueswerelowered,nominallyfrom108to80.SinceplantspecificdataisusedtocalculatetheCF,themarginterm(cr~)canbehalvedfrom34'Fto17'F(RG1.99,Rev.2,Position2.1).ThisdataishighlightedinthesecondsectionofTable1.Usingthenewdata,FPLcalculated(Ref.6)theneutronfluencethatwouldresultinvaluesofRTNDTequaltoorlessthanthelimitingARTsdeterminedinthe15EFPYanalysis.Thenewvaluesoffluencecorrespondto23.6EFPY,asshowninthethirdsectionofTable1.Notethatthelowerlongitudinalweldsarenowthecontrollingmaterialatboththe1/4Tand3/4Tlocations.Sincethe23.6EFPYlimitingRT>>~valueswereequaltoorlessthanthoseusedinthe15EFPYanalysis,thecurrentTechnicalSpecificationP/TlimitcurvesandLTOPanalysiswouldbeapplicableforaperiodnottoexceed23.6EFPYwiththesamemarginofsafetyastheprevious15EFPYanalysis.ThisequivalencecoverstheP/Tlimitsforheatup,cooldown,hydrostatictestandcorecriticaloperation.2~LOWESTSERVICETEMPERATURE,MINIMUMBOLTUPTEMPERATURE,ANDMINIMUMPRESSURELIMITSTheP/Tanalysisfor15EFPYcalculatedthelimitsforlowestservicetemperature,minimumboltuptemperature,andminimumpressurelimitsforreference.Theselimitsarenotbasedonaccumulatedfluenceatthereactorvesselbeltlinematerial,andremainunchanged.ThelowestservicetemperatureisbasedonthemostlimitingRT>>TforthebalanceofRCScomponents,whichistheReactorCoolantPump(RCP).Accumulatedplantoperationdoesnoteffectthiscomponent'smaterialproperties,thereforethelowestservicetemperatureremainsthesame.

=0 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page6of8Theminimumboltuptemperatureisbasedonthehigherstressedregionofthereactorvessel,plusanyeffectsforirradiationeffects(Ref.3)andtestinguncertainty.ThemaximuminitialRT~Tassociatedwiththestressedregionofthereactorvesselflangeis30'F.Forconservatismaminimumboltuptemperatureof80'Fisutilized,whichmorethanaccountsforanyirradiationeffectsandtestinguncertainty(Ref.3).Thefluenceat.theflangeregionisatleasttwoordersofmagnitudelowerthanthepeakvesselfluenceatthebeltlinematerials(i.e.,atfuelcoremidplane).Reference9indicatesthatthefluenceatthetopoftheactivecore,whichislessthan79inchesabovethecoremidplane,decreasesto0.1timesthepeakfluenceatthecoremid-plane.Theflangeisapproximately130inchesabovethetopofthecore,resultinginareductionfromthepeakfluencebyatleasttwoordersofmagnitude.Therefore,theradiationaffectsareminimal,andthe50'Fmarginissufficienttoaccountforanychangesinflangematerialfracturetoughness.Theminimumpressurelimitisthebreakpointbetweentheminimumboltuptemperatureandthelowestservicetemperature,andisdefinedbytheASMEBoilerandPressureVesselCodeas204ofthepre-operationalhydrostaticpressure(Ref.3).Thisvaluewasnotaffectedbyaccumulatedplantoperation.3~CORRECTIONFACTORSSincetheP/TlimitcurvesandLTOPsetpointsarebasedoncoordinatesofpressurizerpressureandindicatedRCSfluidtemperature,correctionfactorsareincludedintheanalysistoaccountforactualconditionsatthelimitingbeltlinematerials.TheP/TlimitsandLTOPanalysisfor15EFPYprovidedforthesecorrectionfactors,whichaddresstheconcernsofNRCInformationNotice(IN)93-58"Non-conservatisminLow-TemperatureOverpressureProtectionforPressurizedMaterReactors"(Ref.8).Thelead/lagtemperaturedifferentialbetweenthevesselbasemetalandtheRCSbulkfluidhasbeenaccountedfor.Pressurecorrectionfactorswerebasedupon:1)thestaticheadduetotheelevationdifferenceofthevesselwalladjacenttotheactivecoreandthepressurizerpressureinstrumentnozzle,and;2)thepressuredifferentialbasedonthenumberofreactorcoolantpumps(RCP's)inoperation.ActualpressureatthecoreregionwouldbehigherthanattheRCShotlegandthepressurizerbytheamountofheadlossdue St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page7of8toRCPflowandthestatichead.Below200'F,flowinducedpressuredropisbasedontwoRCP'sinoperation;above200'F,pressuredropisbasedonthreeRCP'sinoperation.ThisaddressestheconcernsdocumentedinIN93-58.InstrumentuncertaintieshavenotbeenincludedintheP/Tcurves.Theuncertainties(errors)weredeterminedtobeinsignificantrelativetotheconservatismofthemargintermsincludedintheASMESectionIII,AppendixG,method.NRCconcurrencewasdocumentedinthe15EFPYanalysis.Correctionfactorsarenotaffectedbyneutronfluence,and,therefore,remainunchangedbytheextensionofapplicabilityto23.6EFPY.4~LTOPANALYSISTheobjectiveoftheLTOPanalysisfor15EFPYwastoprecludeviolationoftheP/Tlimitsduringstartupandshutdownconditions.TheLTOPanalysisremainsunchangedbytheapplicabilityextensionto23.6EFPYbecausetheP/Tlimitcurvesarenotbeingchanged.Thereforeitisnotnecessarytore-analyzeormodifytheLTOPsystem.ArelaxationoftheLTOPrequirementsfromASMECodeCaseN-514wasincorporatedinthe1993Addenda.Thecodecasepermitsthemaximumpressureinthevesseltobe110%ofthepressuredeterminedtosatisfytheP/TlimitsperAppendixGofSectionXI,ArticleG-2215.The15EFPYLTOPanalysisisinherentlyconservativeinthatthesetpointsforpoweroperatedreliefvalvesandadministrativeandoperationalcontrolsprotectthe1004valueoftheP/Tlimits.5.AMENDINGTHEFOOTNOTEFORUSEOFHPSIASABORATIONPATHOneresultoftheLTOPanalysisfor15EFPYwasarequirementtolimitthemassadditionrateofaHPSIpumpwhenitisusedasaborationpathduringshutdown,withRCSpressureboundaryintegrityestablished.ThemethodtolimitthemassadditionratewastoclosetwoofthefourHPSIheaderisolationvalves.However,thisrequirementonlyapplieswhenRCSpressureboundaryintegrityexists.Thesyntaxusedinfootnote"*"toTS3.1.2.1andTS3.1.2.3couldresultinanunnecessaryrestrictiveinterpretationoftherequirementstoclosetheHPSIheaderisolationvalves.TheproposedrevisionclarifiesthatclosingtwoHPSIvalvesisonlyrequiredunderpart(b)ofthefootnote,e.g.,whennochargingpumpsareoperableandRCSpressureboundaryintegrityexists.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page8of8ConclusionTheproposedperiodofapplicabilityisbasedonprojectionsofirradiationembrittlementforthereactorvesselbeltlinelimitingmaterials.Since1990,whenthecurrentP/Tlimitcurveswereapproved,newmaterialpropertydatahasbecomeavailabletomakebetterpredictionsofembrittlementforthelimitingbeltlinematerials.Usingthenewdata,theperiodofapplicabilityfortheexistingP/TlimitcurvesandLTOPrequirementscanbeextendedfrom15EFPYto23.6EFPYwiththesameanalyzedmarginofsafety.

REFERENCES:

1~2~3~4~5.6.7~8.9.USNRClettertoJ.H.Goldberg,"St.LucieUnit1-IssuanceofAmendmentRe:PressureTemperature(P/T)LimitsandLowTemperatureOverpressureProtection(LTOP)Analysis(TACNo.75386)",datedJunell,1990.(Amendment104)(Notused)FPLlettertoUSNRC,L-89-408,"St.LucieUnit1,DocketNo.50-335,ProposedLicenseAmendment,P-TLimitsandLTOPAnalysis",datedDecember5,1989.FPLlettertoUSNRC,L-93-286,"St.LucieUnit1and2,DocketNo.50-335and50-389,GenericLetter92-01,Revision1,ResponsetoRequestforAdditionalInformation(RAI)",datedNovember15,1993.USNRCLettertoJ.H.Goldberg;GenericLetter(GL)92-01,Revision1,"ReactorVesselStructuralIntegrity,"St.LucieUnit1and2(TACNOSM83505andM83506);May26,1994.FPLcalculationPSL-lFJM-95-004,Rev.0,"St.LucieUnit1ReactorVesselAdjustedReferenceTemperatureandLTOPlimitsat23.6EFPY",dated3/22/95.USNRCGenericLetter92-01"ReactorVesselStructuralIntegrity",Revision1,DatedMarch6,1992.USNRCInformationNotice93-58"Non-conservatisminLow-TemperatureOverpressureProtectionforPressurizedWaterReactors",datedJuly26,1993.CEReportTR-F-MCM-004"FPL,PSL-1EvaluationofIrradiatedCapsuleW97",datedDecember,1983.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsATTACHMENT2TABLE1ST~LUCIEUNIT1REACTORVESSELBELTLINEADJUSTEDREFERENCETEMPERATURESFORDETERMININGPRESSURETEMPERATUREANDLTOPLIMITSCURVES TABLE1:STLUCIEUNIT1REACTORVESSELBELTLINEADJUSTEDREFERENCETEMPERATURESFORDETERMININGPRESSURETEMPERATUREANDLTOPLIMITSCURVES15YEARPT/LTOPCURVESUSINGEXISTING1989ANALYSIS(Originalcriticalvaluesbolded)LOCATIONID¹Cu%Ni%CALC.CFTABLECFINITIALRTndtMARGIN15EFPYPEAKFLUENCE,E19n/cm21/4TFLUENCE15YEARART15YEAR3/4TFLUENCE91/4TART93/4TLowershellsteLowershellsteInttoLowerirthweldsC-8-1C-8-2901360.150.150.230.560.570.11107.8108.4109.820OF20oF-60oF34OF34oF56oF2.05E+192.05E+192.05E+191.22E+191.22E+191.22E+194.34E+18168oF4.34E+181BBOF4.34E+18112OF137oF137OF80OFLowerlongitudinalwelds3054240.30O.B4200.2-56oF65.5oF1.202E+197.16E+182.54E+18191F135oFNEWCHEMISTRYFACTORS5MARGINSBASEDONGL92-01VALUES(ChangesresultingfromnewdatasubmittedwithGL92-01anduseofcapsuledataforplatesbolded)LOCATIONID¹CU%CALC.CFTABLECFINITIALRTndtMARGINLowershellsteLowershellsteInttoLowerirthweldsLowerlongitudinalweldsC-8-1C-8-2901383054240.150.150.230.28o.se79.42o.s779.82o.1184.800.63191.720oF20oF-60oF60oF17oF17oF28oF56oFEQUIVALENTFLUENCE(23.6EFPY)ATTIMEOFREACHINGRT/NDTVALUESUSEDIN1SEFPYCURVESWITHGL92%1CHEMISTRYFACTORS/MARGINS(Ref.7.6)(Newcriticalvaluesbolded)LOCATIONLowershelllateLowershellIsteInttoLowerirthweldsLowerlongitudinalweldsID¹C-8-1C-8-29013B305424Cu%0.150.150.230.28Ni%0.5B0.570.110.63CALC.CFTABLECF79.4279.8284.80191.7INITIALRTndt20OF20oF60oF60oFMARGIN17oF17OF28OF56oF22KBEFPYPEAKFLUENCE,E18n/cm22.82E+192.82E+192.82E+191.783E+191/4TFLUENCE3/4TFLUENCE1.BBE+195.97E+181.68E+195.97E+181.68E+195.97E+181.063E+193.78E+1823.BEFPYART61/4T128oF128oF65oF191oF23.6EFPYART93/4T105OF105OF41OF136oF St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsATTACHMENT3DETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATION St.LucieUnit,1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment3Page1of2DETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATIONPursuantto10CFR50.92,adeterminationmaybemadethataproposedlicenseamendmentinvolvesnosignificanthazardsconsiderationifoperationofthefacilityinaccordancewiththeproposedamendmentwouldnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated;or(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated;or(3)involveasignificantreductioninamarginofsafety.Eachstandardisdiscussedasfollows:(1)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.Thepressure-temperature(P/T)limitcurvesintheTechnicalSpecificationsareconservativelygeneratedinaccordancewiththefracturetoughnessrequirementsof10CFR50AppendixGassupplementedbytheASMECodeSectionXI,AppendixGrecommendations.TheRT>>~valuesarebasedonRegulatoryGuide1.99,Revision2,shiftpredictionandattenuationformula.AnalysesofreactorvesselmaterialirradiationsurveillancespecimensareusedtoverifythevalidityofthefluencepredictionsandtheP/Tlimitcurves.Useofthesecurvesinconjunctionwiththesurveillancespecimenprogramensuresthatthereactorcoolantpressureboundarywillbehaveinanon-brittlemannerandthatthepossibilityofrapidlypropagatingfractureisminimized.Basedontheuseofplantspecificmaterialdata,analysishasdemonstratedthatthecurrentP/Tlimitcurveswillremainconservativeforupto23.6EFPY.InconjunctionwithextendingtheapplicabilityoftheexistingP/Tlimitcurves,thelowtemperatureoverpressureprotection(LTOP)analysisfor15EFPYisalsoextended.TheLTOPanalysisconfirmsthatthecurrentsetpointsforthepower-operatedreliefvalves(PORVs)willprovidetheappropriateoverpressureprotectionatlowReactorCoolantSystem(RCS)temperatures.BecausetheP/Tlimitcurveshavenotchanged,theexistingLTOPvalueshavenotchanged,whichincludethePORVsetpoints,heatupandcooldownrates,anddisablingofnon-essentialcomponents.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment3Page2of2Theproposedamendmentdoesnotchangetheconfigurationoroperationoftheplant,andassuranceisprovidedthatreactorvesselintegritywillbemaintained.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwillnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.(2)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Byapplyingplantspecificdatainthedeterminationofcriticalvesselmateriallimits,theapplicabilityoftheexistingpressuretemperaturelimitsandLTOPrequirementscanbeextended.Thereisnochangeintheconfigurationoroperationofthefacilityasaresultoftheproposedamendment.Theamendmentdoesnotinvolvetheadditionofnewequipmentorthemodificationofexistingequipment,nordoesitalterthedesignofSt.Lucieplantsystems.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.(3)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.Analysishasdemonstratedthatthefracturetoughnessrequirementsof10CFR50AppendixGaresatisfiedandthatconservativeoperatingrestrictionsaremaintainedforthepurposeoflowtemperatureoverpressureprotection.TheP/TlimitcurveswillprovideassurancethattheRCSpressureboundarywillbehaveinaductilemannerandthattheprobabilityofarapidlypropagatingfractureisminimized.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.BasedonthediscussionpresentedaboveandonthesupportingEvaluationofProposedTSChanges,FPLhasconcludedthatthisproposedlicenseamendmentinvolvesnosignificanthazardsconsideration.

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