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{{#Wiki_filter: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
{{#Wiki_filter:PRIDRITY1CCELERATEDRIDSPROCESSIVEG)REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9505240223 DOC.DATE:
95/05/17NOTARIZED:
NOFACXL:50-335 St.LuciePlant,Unit1,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIATION SAGER,D.A.
FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKET05000335


==SUBJECT:==
==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'I''I'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.
Application foramendtolicenseDPR-67,extending applicability ofcurrentRCSpressure/temp limits&maximumallowedRCSheatup&cooldownratesto23.6Effective FullPowerYRsofoperation.
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.
DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR
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.  
/ENCL/SIZE:TITLE:ORSubmittal:
'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.
GeneralDistribution NOTES:RECIPIENT XDCODE/NAME PD2-1LANORRIS,JINTERNAL:
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.
ACRSNRR/DE/EMCB NRR/DSSA/SPLBNUDOCS-ABSTRACT EXTERNAL:
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.  
NOACCOPIESLTTRENCL11116611111111RECXPIENT IDCODE/NAME PD2-1PDFILECENTER01B'NRR/DSSA/SRXB OGC/HDS3NRCPDRCOPIESLTTRENCL111111111011NOTETOALL"RIDS"RECIPIENTS:
=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.
PLEASEHELPUSTOREDUCEiVKSTE!CONTAC'I''I'IIEDOCL'ifENTCONTROLDESk,ROOAfPl-37(EAT.504-0033)TOELIXIINKTEYOL'RNAifL'ROifDISTRIBUTION LIS'I'SI'ORDOCLMEN'I'SYOL'ON"I'lI'.D!TOTALNUMBEROFCOPIESREQUIRED:
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentRCSPressureTemeratureLimitsL-95-139Attachment1Page8of8ConclusionTheproposedperiodofapplicabilityisbasedonprojectionsofirradiationembrittlementforthereactorvesselbeltlinelimitingmaterials.Since1990,whenthecurrentP/Tlimitcurveswereapproved,newmaterialpropertydatahasbecomeavailabletomakebetterpredictionsofembrittlementforthelimitingbeltlinematerials.Usingthenewdata,theperiodofapplicabilityfortheexistingP/TlimitcurvesandLTOPrequirementscanbeextendedfrom15EFPYto23.6EFPYwiththesameanalyzedmarginofsafety.
LTTR.18ENCL17 FloridaPower&LightCompany,P.O.Box128,FortPierce,FL34954-0128 May17,1995L-95-13910CFR50.90U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsPursuantto10CFR50.90,FloridaPower&LightCompany(FPL)requeststoamendFacilityOperating LicenseDPR-67forSt.LucieUnit1byincorporating theattachedTechnical Specifications (TS)revisions.
Theamendment willextendtheapplicability ofthecurrentReactorCoolantSystem(RCS)Pressure/Temperature LimitsandmaximumallowedRCSheatupandcooldownratesto23.6Effective FullPowerYearsofoperation.
Inaddition, administrative changesareproposedforTS3.1.2.1(Boration SystemsFlowPaths-Shutdown) andTS3.1.2.3(Charging Pump-Shutdown) toclarifytheconditions forwhichaHighPressureSafetyInjection pumpmaybeused.Itisrequested thattheproposedamendment, ifapproved, beissuedbyMarch31,1996.Attachment 1isanevaluation oftheproposedTSchanges.Attachment 2isatableofSt.LucieUnit1ReactorVesselBeltlineAdjustedReference Temperatures forDetermining PressureTemperature andLTOPLimitsCurves.Attachment 3isthe"Determination ofNoSignificant HazardsConsideration."
Attachment 4containsacopyoftheappropriate TSpagesmarked-up toshowtheproposedchanges.Theproposedamendment hasbeenreviewedbytheSt.LucieFacilityReviewGroupandtheFloridaPower&LightCompanyNuclearReviewBoard.Inaccordance with10CFR50.91(b)(1),acopyoftheproposedamendment isbeingforwarded totheStateDesigneefortheStateofFlorida.Pleasecontactusifthereareanyquestions aboutthissubmittal.
Verytrulyyours,D.A.aerVicePidentSt.LucePlantanFPLGroupcompany Ig~4 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Page2DAS/RLDAttachments cc:StewartD.Ebneter,RegionalAdministrator, RegionII,USNRC.SeniorResidentInspector, USNRC,St.LuciePlant.Mr.W.A.Passetti, FloridaDepartment ofHealthandRehabilitative Services.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Page3STATEOFFLORIDA))COUNTYOFST.LUCIE)SS~D.A.Sagerbeingfirstdulysworn,deposesandsays:ThatheisVicePresident, St.LuciePlantfortheNuclearDivisionofFloridaPower6LightCompany,theLicenseeherein;Thathehasexecutedtheforegoing documenti thatthestatements madeinthisdocumentaretrueandcorrecttothebestofhisknowledge, information andbelief,andthatheisauthorized toexecutethedocumentonbehalfofsaidLicensee.
D.A.SerSTATEOFFLORIDACOUNTYOFTheforegoing instrument wasacknowledged beforemethisIt~dayof,19'yD.A.Sager,whoispersonalyknowntomeandwhodidtakeanoath.NameofNotaryPublicMyCommission expiresSCommission No.2)Gal1S0~I'yOFFICIALNOTARySEALQy8~<)ALEXISRMOLENDA~COMMISSION NIIMSSRCC156115yCOMMISSION pXIsocT.ggqgg5 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsATTACHMENT 1EVALUATION OFPROPOSEDTSCHANGES 1cSt.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemerature.LimitsL-95-139Attachment 1Page1of8EVALUATION OFPROPOSEDTSCHANGESIntroduction FloridaPowerandLightCompany(FPL)proposestochangetheSt.LucieUnit1Technical Specifications (TS)forReactorCoolantSystem(RCS)Pressure/Temperature LimitsandmaximumallowedRCSheatupandcooldownrates.Theapplicability oftheexistingspecified limitswillbeextendedfrom15Effective FullPowerYears(EFPY)to23.6EFPYofoperation.
Theassociated LowTemperature Overpressure Protection (LTOP)requirements willlikewisebeextended.
Inaddition, administrative changesareproposedforTS3.1.2.1andTS3.1.2.3toclarifytheconditions requiredifaHighPressureSafetyInjection (HPSI)pumpisusedtoestablish aborationflowpathduringoperational Modes5and6.DescritionofChanesMarked-up copiesoftheaffectedTSpagesarecontained inAttachment 4.Adescription oftheproposedchangesfollows:1~TS3.4.9.1currently providesthepressureandtemperature limitsintermsofFigures3.4-2a,3.4-2b,and3.4-3fortheRCS(exceptthepressurizer) duringheatup,cooldown, criticality, andinservice leakandhydrostatic testingfor15EFPY.Theproposedamendment wouldusetheseexistingfigures,as-is,andonlyrevisethetitlebychanging"15EFPYttto>t236EFPY2~3~Footnote"*"isappendedtoTS3.1.2.1andTS3.1.2.3,applicable duringModes5and6,toproviderequirements thatmustbemetiftheborationflowpathfromtheRefueling WaterTank(RWT)isestablished viaasingleHPSIpump.Thisfootnotewillberevisedtomoreclearlyindicatethatthespecified requirements applytothecondition whennochargingpumpsareoperable.
Figure3.1-lbspecifies themaximumallowable heatupandcooldownratesforthecasewhereasingleHPSIpumpisinoperation pursuanttoTS3.1.2.1andTS3.1.2.3.Thelimitofapplicability forthisfigurewillbeindicated byadding"23.6EFPY"tothetitle.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page2of8BackroundThereactorcoolantpressureboundaryisdesignedpursuantto10CFRPart50,AppendixA,DesignCriteria14and31.Thesedesigncriteriarequirethatthereactorcoolantpressureboundarybedesigned, fabricated, erectedandtestedinordertohaveanextremely lowprobability ofabnormalleakage,ofrapidlypropagating failure,andofgrossrupture.Thecriteriaalsorequirethatthereactorcoolantpressureboundarybedesignedwithsufficient margintoassurethat,whenstressed, theboundarybehavesinanon-brittle manner,andthattheprobability ofrapidlypropagating fractureisminimized.
Pressure/Temperature (P/T)limitsaredeveloped toprovideadequatesafetymarginsfortheprevention offractureoftheRCScoolantpressureboundarypursuantto10CFR50,AppendixG,"Fracture Toughness Requirements."
TheASMECodeformsthebasisfortheserequirements.
Themethodtopredictthereactorvesselmaterialirradiation damageisprovidedinUSNRCRegulatory Guide(RG)1.99,Rev.2,"Radiation Embrittlement ofReactorVesselMaterials".
TheexistingP/Tlimitswereimplemented in1990,andarebasedonpredictions forupto15EFPYofreactoroperation.
Itisanticipated thatPSL1willachieve15EFPYofoperation duringthespringof1996.FPLrecalculated thepredicted materialradiation damagebasedonrecent.dataobtainedinresponsetoNRCGenericLetter92OlgReactorVesselStructural Integrity."
UsingthisnewdataandRG1.99,Rev.2,itwasdetermined thattheexistingmaterialradiation damageprediction canbeextendedto23.6EFPYofoperation.
Additional assurance thatRCSP/Tlimitswillnotbeexceededinthelowertemperature operating modesisprovidedbytheLowTemperature Overpressure Protection (LTOP)system.Analysesforthissystemconsidertheinitiation ofassumedenergy-addition andmass-addition transients whileoperating atlowtemperatures inaccordance withStandardReviewPlan5.2.2,Revision2.BasesforProosedTSChanesTheanalysisfortheP/TlimitsandLTOPrequirements for15EFPYwereprovidedwithFPLletterL-89-408(Reference 3),andsubsequently approvedbytheissuanceofAmendment No.104(Reference 1)tothefacilityoperating license.Thebasisfordetermining thattheselimitscanbeextendedto23.6EFPYisprovidedbelowbyreviewing theconclusions ofeachsectionoftheanalysis.  
'II St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page3of8EXTENDING THEAPPLICABILITY OFTHEP/TLIMITCURVESTheP/Tlimitcurveanalysisfor15EFPYwasdeveloped usingtherequirements of10CFR50AppendixG.Thebasiccalculation methodwasreferenced toASMEBoilerandPressureVesselCode,SectionIII,AppendixG(1986).Thecurrentmethodisunchanged exceptthatin1992ASMErelocated AppendixGtoSectionXI,andthereference stressintensity, Km,isnowreferredtoasK.Theirradiated materialproperties fortheP/Tlimitcurvesarebasedupontheirradiation damageprediction methodsofRG1.99,Rev.2,whichareusedtocalculate theadjustedreference temperature (ART)forallreactorvesselbeltlinematerials.
TheseARTpredictions utilizeinitialmaterialtestproperties, materialchemistry, neutronfluenceandmargin,andistheprimarymaterialvariableinputthatisconsidered intheP/Tanalysis.
AhigherARTvalueismorelimitingforplantoperation.
TheARTisdetermined forthereactorvessellimitingbeltlinematerials fortheperiodofapplicability fortheP/Tlimitcurvesbasedonthepredicted neutronfluence.ThesevaluesareshowninthefirstportionofTable1(Attachment 2ofthissubmittal).
Thecontrolling valuesofARTusedfortheP/TlimitcurvesandLTOPanalysisat15EFPYwere191Fatthe1/4Thickness (1/4T)locationand137'Fatthe3/4Thickness (3/4T)location(Ref.3,Attachment 4,page9).Thecontrolling materialwasthelowershelllongitudinal welds(3-203A,BandC,materialheatnumber305424)forthe1/4Tlocationandtwoofthelowershellplates(C-8-1andC-8-2)forthe3/4Tlocation.
Theterm"controlling" meanshavingthehighestARTforagiventimeandpositionwithinthevesselwall.ThehighestART'sarethenusedtodeveloptheP/Tlimitsforthecorresponding period.Notethatindeveloping theP/Tlimits,aboundingmaterial(SA302GradeB)isassumed.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page4of8RG1.99,Rev.2,predictions forARTaredetermined fromthefollowing formulas:
ART=InitialRT~T+dZT~T+MarginInitialRTDTReference temperature
('F)fortheun-irradiated material.
MTgDyMargin(CF)f(0.28-0.10logQ"CF"('F)isthechemistry factor,afunctionofCopperandNickelcontentoftheweldorbasematerial.
"f"isthecalculated neutronfluence(10'/cm,E>1MeV)atthedepthintothevesselfromtheinsidediameterwettedsurfacetothepostulated flaw(surface, 1/4Tand3/4T).Projections offluencearemadeforspecificperiodsoftimeofoperation (EFPY).Thethickness T,withoutthecladding, isconservatively usedtogiveahigherprojected RT~DT.Thequantity('F)tobeaddedtoobtainaconservative upperboundvalueofART.2(0~+0~)"0',=O'Fformeasuredtestvalues,17forgenericdatao'~=17'Fforplateand28'FforweldsNewbeltlineweldmaterialdatabecameavailable asaresultoftheresearchneededtorespondtoNRCGenericLetter92-01.Thisdataishighlighted inthesecondsectionofTable1.Asdescribed below,theplantspecificdatasignificantly reducesthevaluesusedincalculating theART.Forthelimitinglowerlongitudinal welds,thedataincludednewchemistry valuesforcopperandnickel,andanactualinitialRTz,T.ThisnewdatacamefromtheDuquesneLightCo.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page5of8BeaverValleyUnit1reactorvesselsurveillance program(Ref.4),whichhasmaterialidentical totheSt.LucieUnit1lowerlongitudinal welds.AsaresultofusingactualplantspecificRT>>Tdata,theoverallmargintermisreducedfrom65.5'Fto56'F,becausea,becomes0'F.TheinitialRT>>~isloweredfrom-56'Fto-60'F.Thenewchemistry valueswereusedwithexistingSt.Lucie1qualification datatogetnewaveragecopperandnickelvalues(Ref.4),whichloweredthe'Fvaluefrom200.2to191.7.Basedonthesurveillance capsuledataremovedfromtheSt.LucieUnit1reactorvessel,theCF'sforthelimitinglowershellplateswerecalculated andprovidedtoFPLbytheNRC(Ref.5).ThenewCFvalueswerelowered,nominally from108to80.Sinceplantspecificdataisusedtocalculate theCF,themarginterm(cr~)canbehalvedfrom34'Fto17'F(RG1.99,Rev.2,Position2.1).Thisdataishighlighted inthesecondsectionofTable1.Usingthenewdata,FPLcalculated (Ref.6)theneutronfluencethatwouldresultinvaluesofRTNDTequaltoorlessthanthelimitingARTsdetermined inthe15EFPYanalysis.
Thenewvaluesoffluencecorrespond to23.6EFPY,asshowninthethirdsectionofTable1.Notethatthelowerlongitudinal weldsarenowthecontrolling materialatboththe1/4Tand3/4Tlocations.
Sincethe23.6EFPYlimitingRT>>~valueswereequaltoorlessthanthoseusedinthe15EFPYanalysis, thecurrentTechnical Specification P/TlimitcurvesandLTOPanalysiswouldbeapplicable foraperiodnottoexceed23.6EFPYwiththesamemarginofsafetyastheprevious15EFPYanalysis.
Thisequivalence coverstheP/Tlimitsforheatup,cooldown, hydrostatic testandcorecriticaloperation.
2~LOWESTSERVICETEMPERATURE, MINIMUMBOLTUPTEMPERATURE, ANDMINIMUMPRESSURELIMITSTheP/Tanalysisfor15EFPYcalculated thelimitsforlowestservicetemperature, minimumboltuptemperature, andminimumpressurelimitsforreference.
Theselimitsarenotbasedonaccumulated fluenceatthereactorvesselbeltlinematerial, andremainunchanged.
Thelowestservicetemperature isbasedonthemostlimitingRT>>TforthebalanceofRCScomponents, whichistheReactorCoolantPump(RCP).Accumulated plantoperation doesnoteffectthiscomponent's materialproperties, therefore thelowestservicetemperature remainsthesame.  
=0 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page6of8Theminimumboltuptemperature isbasedonthehigherstressedregionofthereactorvessel,plusanyeffectsforirradiation effects(Ref.3)andtestinguncertainty.
ThemaximuminitialRT~Tassociated withthestressedregionofthereactorvesselflangeis30'F.Forconservatism aminimumboltuptemperature of80'Fisutilized, whichmorethanaccountsforanyirradiation effectsandtestinguncertainty (Ref.3).Thefluenceat.theflangeregionisatleasttwoordersofmagnitude lowerthanthepeakvesselfluenceatthebeltlinematerials (i.e.,atfuelcoremidplane).
Reference 9indicates thatthefluenceatthetopoftheactivecore,whichislessthan79inchesabovethecoremidplane, decreases to0.1timesthepeakfluenceatthecoremid-plane.
Theflangeisapproximately 130inchesabovethetopofthecore,resulting inareduction fromthepeakfluencebyatleasttwoordersofmagnitude.
Therefore, theradiation affectsareminimal,andthe50'Fmarginissufficient toaccountforanychangesinflangematerialfracturetoughness.
Theminimumpressurelimitisthebreakpointbetweentheminimumboltuptemperature andthelowestservicetemperature, andisdefinedbytheASMEBoilerandPressureVesselCodeas204ofthepre-operational hydrostatic pressure(Ref.3).Thisvaluewasnotaffectedbyaccumulated plantoperation.
3~CORRECTION FACTORSSincetheP/TlimitcurvesandLTOPsetpoints arebasedoncoordinates ofpressurizer pressureandindicated RCSfluidtemperature, correction factorsareincludedintheanalysistoaccountforactualconditions atthelimitingbeltlinematerials.
TheP/TlimitsandLTOPanalysisfor15EFPYprovidedforthesecorrection factors,whichaddresstheconcernsofNRCInformation Notice(IN)93-58"Non-conservatism inLow-Temperature Overpressure Protection forPressurized MaterReactors" (Ref.8).Thelead/lagtemperature differential betweenthevesselbasemetalandtheRCSbulkfluidhasbeenaccounted for.Pressurecorrection factorswerebasedupon:1)thestaticheadduetotheelevation difference ofthevesselwalladjacenttotheactivecoreandthepressurizer pressureinstrument nozzle,and;2)thepressuredifferential basedonthenumberofreactorcoolantpumps(RCP's)inoperation.
ActualpressureatthecoreregionwouldbehigherthanattheRCShotlegandthepressurizer bytheamountofheadlossdue St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page7of8toRCPflowandthestatichead.Below200'F,flowinducedpressuredropisbasedontwoRCP'sinoperation; above200'F,pressuredropisbasedonthreeRCP'sinoperation.
Thisaddresses theconcernsdocumented inIN93-58.Instrument uncertainties havenotbeenincludedintheP/Tcurves.Theuncertainties (errors)weredetermined tobeinsignificant relativetotheconservatism ofthemargintermsincludedintheASMESectionIII,AppendixG,method.NRCconcurrence wasdocumented inthe15EFPYanalysis.
Correction factorsarenotaffectedbyneutronfluence,and,therefore, remainunchanged bytheextension ofapplicability to23.6EFPY.4~LTOPANALYSISTheobjective oftheLTOPanalysisfor15EFPYwastoprecludeviolation oftheP/Tlimitsduringstartupandshutdownconditions.
TheLTOPanalysisremainsunchanged bytheapplicability extension to23.6EFPYbecausetheP/Tlimitcurvesarenotbeingchanged.Therefore itisnotnecessary tore-analyze ormodifytheLTOPsystem.Arelaxation oftheLTOPrequirements fromASMECodeCaseN-514wasincorporated inthe1993Addenda.Thecodecasepermitsthemaximumpressureinthevesseltobe110%ofthepressuredetermined tosatisfytheP/TlimitsperAppendixGofSectionXI,ArticleG-2215.The15EFPYLTOPanalysisisinherently conservative inthatthesetpoints forpoweroperatedreliefvalvesandadministrative andoperational controlsprotectthe1004valueoftheP/Tlimits.5.AMENDINGTHEFOOTNOTEFORUSEOFHPSIASABORATIONPATHOneresultoftheLTOPanalysisfor15EFPYwasarequirement tolimitthemassadditionrateofaHPSIpumpwhenitisusedasaborationpathduringshutdown, withRCSpressureboundaryintegrity established.
ThemethodtolimitthemassadditionratewastoclosetwoofthefourHPSIheaderisolation valves.However,thisrequirement onlyapplieswhenRCSpressureboundaryintegrity exists.Thesyntaxusedinfootnote"*"toTS3.1.2.1andTS3.1.2.3couldresultinanunnecessary restrictive interpretation oftherequirements toclosetheHPSIheaderisolation valves.Theproposedrevisionclarifies thatclosingtwoHPSIvalvesisonlyrequiredunderpart(b)ofthefootnote, e.g.,whennochargingpumpsareoperableandRCSpressureboundaryintegrity exists.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page8of8Conclusion Theproposedperiodofapplicability isbasedonprojections ofirradiation embrittlement forthereactorvesselbeltlinelimitingmaterials.
Since1990,whenthecurrentP/Tlimitcurveswereapproved, newmaterialpropertydatahasbecomeavailable tomakebetterpredictions ofembrittlement forthelimitingbeltlinematerials.
Usingthenewdata,theperiodofapplicability fortheexistingP/TlimitcurvesandLTOPrequirements canbeextendedfrom15EFPYto23.6EFPYwiththesameanalyzedmarginofsafety.


==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.
 
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.
1~2~3~4~5.6.7~8.9.USNRClettertoJ.H.Goldberg, "St.LucieUnit1-IssuanceofAmendment Re:PressureTemperature (P/T)LimitsandLowTemperature Overpressure Protection (LTOP)Analysis(TACNo.75386)",datedJunell,1990.(Amendment 104)(Notused)FPLlettertoUSNRC,L-89-408, "St.LucieUnit1,DocketNo.50-335,ProposedLicenseAmendment, P-TLimitsandLTOPAnalysis",
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.}}
datedDecember5,1989.FPLlettertoUSNRC,L-93-286, "St.LucieUnit1and2,DocketNo.50-335and50-389,GenericLetter92-01,Revision1,ResponsetoRequestforAdditional Information (RAI)",datedNovember15,1993.USNRCLettertoJ.H.Goldberg; GenericLetter(GL)92-01,Revision1,"ReactorVesselStructural Integrity,"
St.LucieUnit1and2(TACNOSM83505andM83506);May26,1994.FPLcalculation PSL-lFJM-95-004, Rev.0,"St.LucieUnit1ReactorVesselAdjustedReference Temperature andLTOPlimitsat23.6EFPY",dated3/22/95.USNRCGenericLetter92-01"ReactorVesselStructural Integrity",
Revision1,DatedMarch6,1992.USNRCInformation Notice93-58"Non-conservatism inLow-Temperature Overpressure Protection forPressurized WaterReactors",
datedJuly26,1993.CEReportTR-F-MCM-004 "FPL,PSL-1Evaluation ofIrradiated CapsuleW97",datedDecember, 1983.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsATTACHMENT 2TABLE1ST~LUCIEUNIT1REACTORVESSELBELTLINEADJUSTEDREFERENCE TEMPERATURES FORDETERMINING PRESSURETEMPERATURE ANDLTOPLIMITSCURVES TABLE1:STLUCIEUNIT1REACTORVESSELBELTLINEADJUSTEDREFERENCE TEMPERATURES FORDETERMINING PRESSURETEMPERATURE ANDLTOPLIMITSCURVES15YEARPT/LTOPCURVESUSINGEXISTING1989ANALYSIS(Original criticalvaluesbolded)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+18112OF137oF137OF80OFLowerlongitudinal welds3054240.30O.B4200.2-56oF65.5oF1.202E+197.16E+182.54E+18191F135oFNEWCHEMISTRY FACTORS5MARGINSBASEDONGL92-01VALUES(Changesresulting fromnewdatasubmitted withGL92-01anduseofcapsuledataforplatesbolded)LOCATIONID&#xb9;CU%CALC.CFTABLECFINITIALRTndtMARGINLowershellsteLowershellsteInttoLowerirthweldsLowerlongitudinal weldsC-8-1C-8-2901383054240.150.150.230.28o.se79.42o.s779.82o.1184.800.63191.720oF20oF-60oF60oF17oF17oF28oF56oFEQUIVALENT FLUENCE(23.6EFPY)ATTIMEOFREACHINGRT/NDTVALUESUSEDIN1SEFPYCURVESWITHGL92%1CHEMISTRY FACTORS/MARGINS (Ref.7.6)(Newcriticalvaluesbolded)LOCATIONLowershelllateLowershellIsteInttoLowerirthweldsLowerlongitudinal weldsID&#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.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsATTACHMENT 3DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION St.LucieUnit,1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 3Page1of2DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION Pursuantto10CFR50.92, adetermination maybemadethataproposedlicenseamendment involvesnosignificant hazardsconsideration ifoperation ofthefacilityinaccordance withtheproposedamendment wouldnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or(2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated; or(3)involveasignificant reduction inamarginofsafety.Eachstandardisdiscussed asfollows:(1)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
Thepressure-temperature (P/T)limitcurvesintheTechnical Specifications areconservatively generated inaccordance withthefracturetoughness requirements of10CFR50AppendixGassupplemented bytheASMECodeSectionXI,AppendixGrecommendations.
TheRT>>~valuesarebasedonRegulatory Guide1.99,Revision2,shiftprediction andattenuation formula.Analysesofreactorvesselmaterialirradiation surveillance specimens areusedtoverifythevalidityofthefluencepredictions andtheP/Tlimitcurves.Useofthesecurvesinconjunction withthesurveillance specimenprogramensuresthatthereactorcoolantpressureboundarywillbehaveinanon-brittle mannerandthatthepossibility ofrapidlypropagating fractureisminimized.
Basedontheuseofplantspecificmaterialdata,analysishasdemonstrated thatthecurrentP/Tlimitcurveswillremainconservative forupto23.6EFPY.Inconjunction withextending theapplicability oftheexistingP/Tlimitcurves,thelowtemperature overpressure protection (LTOP)analysisfor15EFPYisalsoextended.
TheLTOPanalysisconfirmsthatthecurrentsetpoints forthepower-operated reliefvalves(PORVs)willprovidetheappropriate overpressure protection atlowReactorCoolantSystem(RCS)temperatures.
BecausetheP/Tlimitcurveshavenotchanged,theexistingLTOPvalueshavenotchanged,whichincludethePORVsetpoints, heatupandcooldownrates,anddisabling ofnon-essential components.
St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 3Page2of2Theproposedamendment doesnotchangetheconfiguration oroperation oftheplant,andassurance isprovidedthatreactorvesselintegrity willbemaintained.
Therefore, operation ofthefacilityinaccordance withtheproposedamendment willnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
(2)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Byapplyingplantspecificdatainthedetermination ofcriticalvesselmateriallimits,theapplicability oftheexistingpressuretemperature limitsandLTOPrequirements canbeextended.
Thereisnochangeintheconfiguration oroperation ofthefacilityasaresultoftheproposedamendment.
Theamendment doesnotinvolvetheadditionofnewequipment orthemodification ofexistingequipment, nordoesitalterthedesignofSt.Lucieplantsystems.Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
(3)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Analysishasdemonstrated thatthefracturetoughness requirements of10CFR50AppendixGaresatisfied andthatconservative operating restrictions aremaintained forthepurposeoflowtemperature overpressure protection.
TheP/Tlimitcurveswillprovideassurance thattheRCSpressureboundarywillbehaveinaductilemannerandthattheprobability ofarapidlypropagating fractureisminimized.
Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Basedonthediscussion presented aboveandonthesupporting Evaluation ofProposedTSChanges,FPLhasconcluded thatthisproposedlicenseamendment involvesnosignificant hazardsconsideration.}}

Revision as of 14:56, 29 June 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)REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9505240223 DOC.DATE:

95/05/17NOTARIZED:

NOFACXL:50-335 St.LuciePlant,Unit1,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIATION SAGER,D.A.

FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKET05000335

SUBJECT:

Application foramendtolicenseDPR-67,extending applicability ofcurrentRCSpressure/temp limits&maximumallowedRCSheatup&cooldownratesto23.6Effective FullPowerYRsofoperation.

DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR

/ENCL/SIZE:TITLE:ORSubmittal:

GeneralDistribution NOTES:RECIPIENT XDCODE/NAME PD2-1LANORRIS,JINTERNAL:

ACRSNRR/DE/EMCB NRR/DSSA/SPLBNUDOCS-ABSTRACT EXTERNAL:

NOACCOPIESLTTRENCL11116611111111RECXPIENT IDCODE/NAME PD2-1PDFILECENTER01B'NRR/DSSA/SRXB OGC/HDS3NRCPDRCOPIESLTTRENCL111111111011NOTETOALL"RIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEiVKSTE!CONTAC'II'IIEDOCL'ifENTCONTROLDESk,ROOAfPl-37(EAT.504-0033)TOELIXIINKTEYOL'RNAifL'ROifDISTRIBUTION LIS'I'SI'ORDOCLMEN'I'SYOL'ON"I'lI'.D!TOTALNUMBEROFCOPIESREQUIRED:

LTTR.18ENCL17 FloridaPower&LightCompany,P.O.Box128,FortPierce,FL34954-0128 May17,1995L-95-13910CFR50.90U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsPursuantto10CFR50.90,FloridaPower&LightCompany(FPL)requeststoamendFacilityOperating LicenseDPR-67forSt.LucieUnit1byincorporating theattachedTechnical Specifications (TS)revisions.

Theamendment willextendtheapplicability ofthecurrentReactorCoolantSystem(RCS)Pressure/Temperature LimitsandmaximumallowedRCSheatupandcooldownratesto23.6Effective FullPowerYearsofoperation.

Inaddition, administrative changesareproposedforTS3.1.2.1(Boration SystemsFlowPaths-Shutdown) andTS3.1.2.3(Charging Pump-Shutdown) toclarifytheconditions forwhichaHighPressureSafetyInjection pumpmaybeused.Itisrequested thattheproposedamendment, ifapproved, beissuedbyMarch31,1996.Attachment 1isanevaluation oftheproposedTSchanges.Attachment 2isatableofSt.LucieUnit1ReactorVesselBeltlineAdjustedReference Temperatures forDetermining PressureTemperature andLTOPLimitsCurves.Attachment 3isthe"Determination ofNoSignificant HazardsConsideration."

Attachment 4containsacopyoftheappropriate TSpagesmarked-up toshowtheproposedchanges.Theproposedamendment hasbeenreviewedbytheSt.LucieFacilityReviewGroupandtheFloridaPower&LightCompanyNuclearReviewBoard.Inaccordance with10CFR50.91(b)(1),acopyoftheproposedamendment isbeingforwarded totheStateDesigneefortheStateofFlorida.Pleasecontactusifthereareanyquestions aboutthissubmittal.

Verytrulyyours,D.A.aerVicePidentSt.LucePlantanFPLGroupcompany Ig~4 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Page2DAS/RLDAttachments cc:StewartD.Ebneter,RegionalAdministrator, RegionII,USNRC.SeniorResidentInspector, USNRC,St.LuciePlant.Mr.W.A.Passetti, FloridaDepartment ofHealthandRehabilitative Services.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Page3STATEOFFLORIDA))COUNTYOFST.LUCIE)SS~D.A.Sagerbeingfirstdulysworn,deposesandsays:ThatheisVicePresident, St.LuciePlantfortheNuclearDivisionofFloridaPower6LightCompany,theLicenseeherein;Thathehasexecutedtheforegoing documenti thatthestatements madeinthisdocumentaretrueandcorrecttothebestofhisknowledge, information andbelief,andthatheisauthorized toexecutethedocumentonbehalfofsaidLicensee.

D.A.SerSTATEOFFLORIDACOUNTYOFTheforegoing instrument wasacknowledged beforemethisIt~dayof,19'yD.A.Sager,whoispersonalyknowntomeandwhodidtakeanoath.NameofNotaryPublicMyCommission expiresSCommission No.2)Gal1S0~I'yOFFICIALNOTARySEALQy8~<)ALEXISRMOLENDA~COMMISSION NIIMSSRCC156115yCOMMISSION pXIsocT.ggqgg5 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsATTACHMENT 1EVALUATION OFPROPOSEDTSCHANGES 1cSt.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemerature.LimitsL-95-139Attachment 1Page1of8EVALUATION OFPROPOSEDTSCHANGESIntroduction FloridaPowerandLightCompany(FPL)proposestochangetheSt.LucieUnit1Technical Specifications (TS)forReactorCoolantSystem(RCS)Pressure/Temperature LimitsandmaximumallowedRCSheatupandcooldownrates.Theapplicability oftheexistingspecified limitswillbeextendedfrom15Effective FullPowerYears(EFPY)to23.6EFPYofoperation.

Theassociated LowTemperature Overpressure Protection (LTOP)requirements willlikewisebeextended.

Inaddition, administrative changesareproposedforTS3.1.2.1andTS3.1.2.3toclarifytheconditions requiredifaHighPressureSafetyInjection (HPSI)pumpisusedtoestablish aborationflowpathduringoperational Modes5and6.DescritionofChanesMarked-up copiesoftheaffectedTSpagesarecontained inAttachment 4.Adescription oftheproposedchangesfollows:1~TS3.4.9.1currently providesthepressureandtemperature limitsintermsofFigures3.4-2a,3.4-2b,and3.4-3fortheRCS(exceptthepressurizer) duringheatup,cooldown, criticality, andinservice leakandhydrostatic testingfor15EFPY.Theproposedamendment wouldusetheseexistingfigures,as-is,andonlyrevisethetitlebychanging"15EFPYttto>t236EFPY2~3~Footnote"*"isappendedtoTS3.1.2.1andTS3.1.2.3,applicable duringModes5and6,toproviderequirements thatmustbemetiftheborationflowpathfromtheRefueling WaterTank(RWT)isestablished viaasingleHPSIpump.Thisfootnotewillberevisedtomoreclearlyindicatethatthespecified requirements applytothecondition whennochargingpumpsareoperable.

Figure3.1-lbspecifies themaximumallowable heatupandcooldownratesforthecasewhereasingleHPSIpumpisinoperation pursuanttoTS3.1.2.1andTS3.1.2.3.Thelimitofapplicability forthisfigurewillbeindicated byadding"23.6EFPY"tothetitle.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page2of8BackroundThereactorcoolantpressureboundaryisdesignedpursuantto10CFRPart50,AppendixA,DesignCriteria14and31.Thesedesigncriteriarequirethatthereactorcoolantpressureboundarybedesigned, fabricated, erectedandtestedinordertohaveanextremely lowprobability ofabnormalleakage,ofrapidlypropagating failure,andofgrossrupture.Thecriteriaalsorequirethatthereactorcoolantpressureboundarybedesignedwithsufficient margintoassurethat,whenstressed, theboundarybehavesinanon-brittle manner,andthattheprobability ofrapidlypropagating fractureisminimized.

Pressure/Temperature (P/T)limitsaredeveloped toprovideadequatesafetymarginsfortheprevention offractureoftheRCScoolantpressureboundarypursuantto10CFR50,AppendixG,"Fracture Toughness Requirements."

TheASMECodeformsthebasisfortheserequirements.

Themethodtopredictthereactorvesselmaterialirradiation damageisprovidedinUSNRCRegulatory Guide(RG)1.99,Rev.2,"Radiation Embrittlement ofReactorVesselMaterials".

TheexistingP/Tlimitswereimplemented in1990,andarebasedonpredictions forupto15EFPYofreactoroperation.

Itisanticipated thatPSL1willachieve15EFPYofoperation duringthespringof1996.FPLrecalculated thepredicted materialradiation damagebasedonrecent.dataobtainedinresponsetoNRCGenericLetter92OlgReactorVesselStructural Integrity."

UsingthisnewdataandRG1.99,Rev.2,itwasdetermined thattheexistingmaterialradiation damageprediction canbeextendedto23.6EFPYofoperation.

Additional assurance thatRCSP/Tlimitswillnotbeexceededinthelowertemperature operating modesisprovidedbytheLowTemperature Overpressure Protection (LTOP)system.Analysesforthissystemconsidertheinitiation ofassumedenergy-addition andmass-addition transients whileoperating atlowtemperatures inaccordance withStandardReviewPlan5.2.2,Revision2.BasesforProosedTSChanesTheanalysisfortheP/TlimitsandLTOPrequirements for15EFPYwereprovidedwithFPLletterL-89-408(Reference 3),andsubsequently approvedbytheissuanceofAmendment No.104(Reference 1)tothefacilityoperating license.Thebasisfordetermining thattheselimitscanbeextendedto23.6EFPYisprovidedbelowbyreviewing theconclusions ofeachsectionoftheanalysis.

'II St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page3of8EXTENDING THEAPPLICABILITY OFTHEP/TLIMITCURVESTheP/Tlimitcurveanalysisfor15EFPYwasdeveloped usingtherequirements of10CFR50AppendixG.Thebasiccalculation methodwasreferenced toASMEBoilerandPressureVesselCode,SectionIII,AppendixG(1986).Thecurrentmethodisunchanged exceptthatin1992ASMErelocated AppendixGtoSectionXI,andthereference stressintensity, Km,isnowreferredtoasK.Theirradiated materialproperties fortheP/Tlimitcurvesarebasedupontheirradiation damageprediction methodsofRG1.99,Rev.2,whichareusedtocalculate theadjustedreference temperature (ART)forallreactorvesselbeltlinematerials.

TheseARTpredictions utilizeinitialmaterialtestproperties, materialchemistry, neutronfluenceandmargin,andistheprimarymaterialvariableinputthatisconsidered intheP/Tanalysis.

AhigherARTvalueismorelimitingforplantoperation.

TheARTisdetermined forthereactorvessellimitingbeltlinematerials fortheperiodofapplicability fortheP/Tlimitcurvesbasedonthepredicted neutronfluence.ThesevaluesareshowninthefirstportionofTable1(Attachment 2ofthissubmittal).

Thecontrolling valuesofARTusedfortheP/TlimitcurvesandLTOPanalysisat15EFPYwere191Fatthe1/4Thickness (1/4T)locationand137'Fatthe3/4Thickness (3/4T)location(Ref.3,Attachment 4,page9).Thecontrolling materialwasthelowershelllongitudinal welds(3-203A,BandC,materialheatnumber305424)forthe1/4Tlocationandtwoofthelowershellplates(C-8-1andC-8-2)forthe3/4Tlocation.

Theterm"controlling" meanshavingthehighestARTforagiventimeandpositionwithinthevesselwall.ThehighestART'sarethenusedtodeveloptheP/Tlimitsforthecorresponding period.Notethatindeveloping theP/Tlimits,aboundingmaterial(SA302GradeB)isassumed.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page4of8RG1.99,Rev.2,predictions forARTaredetermined fromthefollowing formulas:

ART=InitialRT~T+dZT~T+MarginInitialRTDTReference temperature

('F)fortheun-irradiated material.

MTgDyMargin(CF)f(0.28-0.10logQ"CF"('F)isthechemistry factor,afunctionofCopperandNickelcontentoftheweldorbasematerial.

"f"isthecalculated neutronfluence(10'/cm,E>1MeV)atthedepthintothevesselfromtheinsidediameterwettedsurfacetothepostulated flaw(surface, 1/4Tand3/4T).Projections offluencearemadeforspecificperiodsoftimeofoperation (EFPY).Thethickness T,withoutthecladding, isconservatively usedtogiveahigherprojected RT~DT.Thequantity('F)tobeaddedtoobtainaconservative upperboundvalueofART.2(0~+0~)"0',=O'Fformeasuredtestvalues,17forgenericdatao'~=17'Fforplateand28'FforweldsNewbeltlineweldmaterialdatabecameavailable asaresultoftheresearchneededtorespondtoNRCGenericLetter92-01.Thisdataishighlighted inthesecondsectionofTable1.Asdescribed below,theplantspecificdatasignificantly reducesthevaluesusedincalculating theART.Forthelimitinglowerlongitudinal welds,thedataincludednewchemistry valuesforcopperandnickel,andanactualinitialRTz,T.ThisnewdatacamefromtheDuquesneLightCo.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page5of8BeaverValleyUnit1reactorvesselsurveillance program(Ref.4),whichhasmaterialidentical totheSt.LucieUnit1lowerlongitudinal welds.AsaresultofusingactualplantspecificRT>>Tdata,theoverallmargintermisreducedfrom65.5'Fto56'F,becausea,becomes0'F.TheinitialRT>>~isloweredfrom-56'Fto-60'F.Thenewchemistry valueswereusedwithexistingSt.Lucie1qualification datatogetnewaveragecopperandnickelvalues(Ref.4),whichloweredthe'Fvaluefrom200.2to191.7.Basedonthesurveillance capsuledataremovedfromtheSt.LucieUnit1reactorvessel,theCF'sforthelimitinglowershellplateswerecalculated andprovidedtoFPLbytheNRC(Ref.5).ThenewCFvalueswerelowered,nominally from108to80.Sinceplantspecificdataisusedtocalculate theCF,themarginterm(cr~)canbehalvedfrom34'Fto17'F(RG1.99,Rev.2,Position2.1).Thisdataishighlighted inthesecondsectionofTable1.Usingthenewdata,FPLcalculated (Ref.6)theneutronfluencethatwouldresultinvaluesofRTNDTequaltoorlessthanthelimitingARTsdetermined inthe15EFPYanalysis.

Thenewvaluesoffluencecorrespond to23.6EFPY,asshowninthethirdsectionofTable1.Notethatthelowerlongitudinal weldsarenowthecontrolling materialatboththe1/4Tand3/4Tlocations.

Sincethe23.6EFPYlimitingRT>>~valueswereequaltoorlessthanthoseusedinthe15EFPYanalysis, thecurrentTechnical Specification P/TlimitcurvesandLTOPanalysiswouldbeapplicable foraperiodnottoexceed23.6EFPYwiththesamemarginofsafetyastheprevious15EFPYanalysis.

Thisequivalence coverstheP/Tlimitsforheatup,cooldown, hydrostatic testandcorecriticaloperation.

2~LOWESTSERVICETEMPERATURE, MINIMUMBOLTUPTEMPERATURE, ANDMINIMUMPRESSURELIMITSTheP/Tanalysisfor15EFPYcalculated thelimitsforlowestservicetemperature, minimumboltuptemperature, andminimumpressurelimitsforreference.

Theselimitsarenotbasedonaccumulated fluenceatthereactorvesselbeltlinematerial, andremainunchanged.

Thelowestservicetemperature isbasedonthemostlimitingRT>>TforthebalanceofRCScomponents, whichistheReactorCoolantPump(RCP).Accumulated plantoperation doesnoteffectthiscomponent's materialproperties, therefore thelowestservicetemperature remainsthesame.

=0 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page6of8Theminimumboltuptemperature isbasedonthehigherstressedregionofthereactorvessel,plusanyeffectsforirradiation effects(Ref.3)andtestinguncertainty.

ThemaximuminitialRT~Tassociated withthestressedregionofthereactorvesselflangeis30'F.Forconservatism aminimumboltuptemperature of80'Fisutilized, whichmorethanaccountsforanyirradiation effectsandtestinguncertainty (Ref.3).Thefluenceat.theflangeregionisatleasttwoordersofmagnitude lowerthanthepeakvesselfluenceatthebeltlinematerials (i.e.,atfuelcoremidplane).

Reference 9indicates thatthefluenceatthetopoftheactivecore,whichislessthan79inchesabovethecoremidplane, decreases to0.1timesthepeakfluenceatthecoremid-plane.

Theflangeisapproximately 130inchesabovethetopofthecore,resulting inareduction fromthepeakfluencebyatleasttwoordersofmagnitude.

Therefore, theradiation affectsareminimal,andthe50'Fmarginissufficient toaccountforanychangesinflangematerialfracturetoughness.

Theminimumpressurelimitisthebreakpointbetweentheminimumboltuptemperature andthelowestservicetemperature, andisdefinedbytheASMEBoilerandPressureVesselCodeas204ofthepre-operational hydrostatic pressure(Ref.3).Thisvaluewasnotaffectedbyaccumulated plantoperation.

3~CORRECTION FACTORSSincetheP/TlimitcurvesandLTOPsetpoints arebasedoncoordinates ofpressurizer pressureandindicated RCSfluidtemperature, correction factorsareincludedintheanalysistoaccountforactualconditions atthelimitingbeltlinematerials.

TheP/TlimitsandLTOPanalysisfor15EFPYprovidedforthesecorrection factors,whichaddresstheconcernsofNRCInformation Notice(IN)93-58"Non-conservatism inLow-Temperature Overpressure Protection forPressurized MaterReactors" (Ref.8).Thelead/lagtemperature differential betweenthevesselbasemetalandtheRCSbulkfluidhasbeenaccounted for.Pressurecorrection factorswerebasedupon:1)thestaticheadduetotheelevation difference ofthevesselwalladjacenttotheactivecoreandthepressurizer pressureinstrument nozzle,and;2)thepressuredifferential basedonthenumberofreactorcoolantpumps(RCP's)inoperation.

ActualpressureatthecoreregionwouldbehigherthanattheRCShotlegandthepressurizer bytheamountofheadlossdue St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page7of8toRCPflowandthestatichead.Below200'F,flowinducedpressuredropisbasedontwoRCP'sinoperation; above200'F,pressuredropisbasedonthreeRCP'sinoperation.

Thisaddresses theconcernsdocumented inIN93-58.Instrument uncertainties havenotbeenincludedintheP/Tcurves.Theuncertainties (errors)weredetermined tobeinsignificant relativetotheconservatism ofthemargintermsincludedintheASMESectionIII,AppendixG,method.NRCconcurrence wasdocumented inthe15EFPYanalysis.

Correction factorsarenotaffectedbyneutronfluence,and,therefore, remainunchanged bytheextension ofapplicability to23.6EFPY.4~LTOPANALYSISTheobjective oftheLTOPanalysisfor15EFPYwastoprecludeviolation oftheP/Tlimitsduringstartupandshutdownconditions.

TheLTOPanalysisremainsunchanged bytheapplicability extension to23.6EFPYbecausetheP/Tlimitcurvesarenotbeingchanged.Therefore itisnotnecessary tore-analyze ormodifytheLTOPsystem.Arelaxation oftheLTOPrequirements fromASMECodeCaseN-514wasincorporated inthe1993Addenda.Thecodecasepermitsthemaximumpressureinthevesseltobe110%ofthepressuredetermined tosatisfytheP/TlimitsperAppendixGofSectionXI,ArticleG-2215.The15EFPYLTOPanalysisisinherently conservative inthatthesetpoints forpoweroperatedreliefvalvesandadministrative andoperational controlsprotectthe1004valueoftheP/Tlimits.5.AMENDINGTHEFOOTNOTEFORUSEOFHPSIASABORATIONPATHOneresultoftheLTOPanalysisfor15EFPYwasarequirement tolimitthemassadditionrateofaHPSIpumpwhenitisusedasaborationpathduringshutdown, withRCSpressureboundaryintegrity established.

ThemethodtolimitthemassadditionratewastoclosetwoofthefourHPSIheaderisolation valves.However,thisrequirement onlyapplieswhenRCSpressureboundaryintegrity exists.Thesyntaxusedinfootnote"*"toTS3.1.2.1andTS3.1.2.3couldresultinanunnecessary restrictive interpretation oftherequirements toclosetheHPSIheaderisolation valves.Theproposedrevisionclarifies thatclosingtwoHPSIvalvesisonlyrequiredunderpart(b)ofthefootnote, e.g.,whennochargingpumpsareoperableandRCSpressureboundaryintegrity exists.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 1Page8of8Conclusion Theproposedperiodofapplicability isbasedonprojections ofirradiation embrittlement forthereactorvesselbeltlinelimitingmaterials.

Since1990,whenthecurrentP/Tlimitcurveswereapproved, newmaterialpropertydatahasbecomeavailable tomakebetterpredictions ofembrittlement forthelimitingbeltlinematerials.

Usingthenewdata,theperiodofapplicability fortheexistingP/TlimitcurvesandLTOPrequirements canbeextendedfrom15EFPYto23.6EFPYwiththesameanalyzedmarginofsafety.

REFERENCES:

1~2~3~4~5.6.7~8.9.USNRClettertoJ.H.Goldberg, "St.LucieUnit1-IssuanceofAmendment Re:PressureTemperature (P/T)LimitsandLowTemperature Overpressure Protection (LTOP)Analysis(TACNo.75386)",datedJunell,1990.(Amendment 104)(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,ResponsetoRequestforAdditional Information (RAI)",datedNovember15,1993.USNRCLettertoJ.H.Goldberg; GenericLetter(GL)92-01,Revision1,"ReactorVesselStructural Integrity,"

St.LucieUnit1and2(TACNOSM83505andM83506);May26,1994.FPLcalculation PSL-lFJM-95-004, Rev.0,"St.LucieUnit1ReactorVesselAdjustedReference Temperature andLTOPlimitsat23.6EFPY",dated3/22/95.USNRCGenericLetter92-01"ReactorVesselStructural Integrity",

Revision1,DatedMarch6,1992.USNRCInformation Notice93-58"Non-conservatism inLow-Temperature Overpressure Protection forPressurized WaterReactors",

datedJuly26,1993.CEReportTR-F-MCM-004 "FPL,PSL-1Evaluation ofIrradiated CapsuleW97",datedDecember, 1983.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsATTACHMENT 2TABLE1ST~LUCIEUNIT1REACTORVESSELBELTLINEADJUSTEDREFERENCE TEMPERATURES FORDETERMINING PRESSURETEMPERATURE ANDLTOPLIMITSCURVES TABLE1:STLUCIEUNIT1REACTORVESSELBELTLINEADJUSTEDREFERENCE TEMPERATURES FORDETERMINING PRESSURETEMPERATURE ANDLTOPLIMITSCURVES15YEARPT/LTOPCURVESUSINGEXISTING1989ANALYSIS(Original criticalvaluesbolded)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+18112OF137oF137OF80OFLowerlongitudinal welds3054240.30O.B4200.2-56oF65.5oF1.202E+197.16E+182.54E+18191F135oFNEWCHEMISTRY FACTORS5MARGINSBASEDONGL92-01VALUES(Changesresulting fromnewdatasubmitted withGL92-01anduseofcapsuledataforplatesbolded)LOCATIONID¹CU%CALC.CFTABLECFINITIALRTndtMARGINLowershellsteLowershellsteInttoLowerirthweldsLowerlongitudinal weldsC-8-1C-8-2901383054240.150.150.230.28o.se79.42o.s779.82o.1184.800.63191.720oF20oF-60oF60oF17oF17oF28oF56oFEQUIVALENT FLUENCE(23.6EFPY)ATTIMEOFREACHINGRT/NDTVALUESUSEDIN1SEFPYCURVESWITHGL92%1CHEMISTRY FACTORS/MARGINS (Ref.7.6)(Newcriticalvaluesbolded)LOCATIONLowershelllateLowershellIsteInttoLowerirthweldsLowerlongitudinal weldsID¹C-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.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsATTACHMENT 3DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION St.LucieUnit,1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 3Page1of2DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION Pursuantto10CFR50.92, adetermination maybemadethataproposedlicenseamendment involvesnosignificant hazardsconsideration ifoperation ofthefacilityinaccordance withtheproposedamendment wouldnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or(2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated; or(3)involveasignificant reduction inamarginofsafety.Eachstandardisdiscussed asfollows:(1)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

Thepressure-temperature (P/T)limitcurvesintheTechnical Specifications areconservatively generated inaccordance withthefracturetoughness requirements of10CFR50AppendixGassupplemented bytheASMECodeSectionXI,AppendixGrecommendations.

TheRT>>~valuesarebasedonRegulatory Guide1.99,Revision2,shiftprediction andattenuation formula.Analysesofreactorvesselmaterialirradiation surveillance specimens areusedtoverifythevalidityofthefluencepredictions andtheP/Tlimitcurves.Useofthesecurvesinconjunction withthesurveillance specimenprogramensuresthatthereactorcoolantpressureboundarywillbehaveinanon-brittle mannerandthatthepossibility ofrapidlypropagating fractureisminimized.

Basedontheuseofplantspecificmaterialdata,analysishasdemonstrated thatthecurrentP/Tlimitcurveswillremainconservative forupto23.6EFPY.Inconjunction withextending theapplicability oftheexistingP/Tlimitcurves,thelowtemperature overpressure protection (LTOP)analysisfor15EFPYisalsoextended.

TheLTOPanalysisconfirmsthatthecurrentsetpoints forthepower-operated reliefvalves(PORVs)willprovidetheappropriate overpressure protection atlowReactorCoolantSystem(RCS)temperatures.

BecausetheP/Tlimitcurveshavenotchanged,theexistingLTOPvalueshavenotchanged,whichincludethePORVsetpoints, heatupandcooldownrates,anddisabling ofnon-essential components.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment RCSPressureTemeratureLimitsL-95-139Attachment 3Page2of2Theproposedamendment doesnotchangetheconfiguration oroperation oftheplant,andassurance isprovidedthatreactorvesselintegrity willbemaintained.

Therefore, operation ofthefacilityinaccordance withtheproposedamendment willnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

(2)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Byapplyingplantspecificdatainthedetermination ofcriticalvesselmateriallimits,theapplicability oftheexistingpressuretemperature limitsandLTOPrequirements canbeextended.

Thereisnochangeintheconfiguration oroperation ofthefacilityasaresultoftheproposedamendment.

Theamendment doesnotinvolvetheadditionofnewequipment orthemodification ofexistingequipment, nordoesitalterthedesignofSt.Lucieplantsystems.Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

(3)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Analysishasdemonstrated thatthefracturetoughness requirements of10CFR50AppendixGaresatisfied andthatconservative operating restrictions aremaintained forthepurposeoflowtemperature overpressure protection.

TheP/Tlimitcurveswillprovideassurance thattheRCSpressureboundarywillbehaveinaductilemannerandthattheprobability ofarapidlypropagating fractureisminimized.

Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Basedonthediscussion presented aboveandonthesupporting Evaluation ofProposedTSChanges,FPLhasconcluded thatthisproposedlicenseamendment involvesnosignificant hazardsconsideration.

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