ML17229A922

Application for Amend to License DPR-67,revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1

ML17229A922
Person / Time
Site:	Saint Lucie
Issue date:	11/22/1998
From:	STALL J A FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17229A923	List: ML17229A922 ML17229A925
References
L-98-283, NUDOCS 9812010024
Download: ML17229A922 (26)

Text

CATEGORY1tREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)

SUBJECT:

ApplicationforamendtolicenseDPR-67,revisingthermalmarginSLlinesofTSFigure2.1-1toreflectincreaseinvalueofdesignminRCSflowfrom345,000gpmto365,000gpm&changeflowratesstatedinTables2.2-1&.3.2-1.DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionNOTES:jpi'rACCESSIONNBR:9812010024DOC.DATE:98/11/22NOTARIZED:YESFACIL:50-335St.LuciePlant,Unit1,FloridaPower&.LightCo.AUTH.NAlrgAUTHORAFFILIATIONSTALL,J.A.FloridaPower6LightCo.RECIP.NAMERECIPIENTAFFILIATIONRecordsManagementBranch(DocumentControlDesk)DOCKET050003352,TERECIPIENTIDCODE/NAMEPD2-3LAGLEAVES,WCOPIESLTTRENCL1111'ECIPIENTIDCODE/NAMEPD2-3PDCOPIESLTTRENCL11INTERNAL:ACRSNRR/DE/ECGB/ANRR/DRCH/HICBNRR/DSSA/SRZBOGC/HDS3EXTERNAL:NOAC111111111011FILECETER01EKCBNRR/DSSA/SPLBNUDOCS-ABSTRACTNRCPDR11111,1111~1U'OTETOALL"RZDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTETHTOHAVEYOURNAMEORORGANIZATIONREMOVEDFROMDISTRIBUTIONLISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION,CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION415-2083TOTALNUMBEROFCOPIESREQUIRED:LTTR14ENCL13 4(

0FloridaPower6tLightCompany,6351S.OceanDrive,JensenBeach,FL34957November22,1998L-98-28310CFR50.90U.S.NuclearRegulatoryCommissionATTN:DocumentControlDeskWashington,D.C.20555Re:St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentCSuoadTSUdaePursuantto10CFR50.90,FloridaPower8LightCompany(FPL)requeststoamendFacilityOperatingLicenseDPR-67forSt.LucieUnit1byincorporatingtheattachedTechnicalSpecifications(TS)revisions.TheamendmentwillrevisetheThermalMarginSafetyLimitLinesofTSFigure2.1-1toreflectanincreaseinthevalueofdesignminimumReactorCoolantSystem(RCS)flowfrom345,000gpmto365,000gpm,andchangetheflowratesstatedinTables2.2-1and3.2-1accordingly.ThereactorprotectiveinstrumentationReactorCoolantFlow-Lowtripsetpointlimitswillbechangedfrom93%to95%ofdesignRCSflow.Theseproposedchangesareintendedtorecovertheanalysismarginlostasaresultofchangestotheflowandlowflowtripsetpointlimitsthatweremadenecessarybysteamgeneratortubepluggingovermorethan20yearsofplantoperation.ThesteamgeneratorsatSt.LucieUnit1werereplacedduringthe1997refuelingoutageforthecurrentoperatingcycleand,duetotheresultantincreaseinRCSflow,theproposedchangeswillbenefitthesafetyanalyseswhilemaintainingsufficientoperatingmarginsrelatedtotheseparameters.Otherchangesproposedinthislicenseamendmentinclude:arevisiontoTS1.10toupdatethereferencefordoseconversionfactorsusedinDoseEquivalentIodine-131calculationsfromthoselistedinTableIIIofTID-14844tothoselistedinICRP-30;andadministrativechangesthatdeletethenumericalvalueofcdgcalttyanalysisuncertaintydescribedinfuelstoragedesignfeaturesTS5,6.1.s.t,/updatetheanalyticalmethodsusedfordeterminingcoreoperatinglimitslistedinadministrativecontrolsTS6.9.1.11,andreviseLimitingSafetySystemSettingsBases2.2fortheSteamGeneratorPressure-Lowtriptodeletethenumericalvalueofsteampressuredescnbedasthefullloadoperatingpoint.PleasenotethattwooftheTopicalReportsshownintherevisedlistofanalyticalmethodsforTS6.9.1.11.barecurrentlybeingreviewedbytheNRCstaff.ThereportsareidentifiedinPart3.6ofAttachment1(page6of11).IncludingtheseTopicalReportsinTS6.9.1.11.b,therefore,iscontingent.uponcompletionofthestaff'sreviewofbothreportsandfinalapprovalthereof.Itisrequestedthattheproposedamendment,ifapproved,beissuedbyAugust15,1999.Attachment1isanevaluationoftheproposedTSchanges.Attachment2isthe"DeterminationofNoSignificantHazardsConsideration."Attachment3containsacopyoftheaffectedTSpagesmarked-uptoshowtheproposedchanges.pp0Cgv~V~.98i20i0024'ii8ii222tPDRADQCK05000335PDRIanFPLGroupcompany

~es~ss St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentCSuoadaeL-98-283Page2TheproposedamendmenthasbeenreviewedbytheSt.LucieFacilityReviewGroupandtheFloridaPower8LightCompanyNuclearReviewBoard.Inaccordancewith10CFR50.91(b)(1),acopyoftheproposedamendmentisbeingforwardedtotheStateDesigneefortheStateofFlorida.Pleasecontactusifthereareanyquestionsaboutthissubmittal.Verytrulyyours,J.A.StallVicePresidentSt.LuciePlantJAS/RLDAttachmentscc:RegionalAdministrator,RegionII,USNRC.SeniorResidentInspector,USNRC,St.LuciePlant.Mr.W.A.Passetti,FloridaDepartmentofHealthandRehabilitativeServices.

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~~St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentCSuowadSUdateL-98-283Page3STATEOFFLORIDA))ss.COUNTYOFST.LUCIE)J.A.Stallbeingfirstdulysworn,deposesandsays:ThatheisVicePresident,St.LuciePlant,fortheNuclearDivisionofFloridaPower8LightCompany,theLicenseeherein;Thathehasexecutedtheforegoingdocument;thatthestatementsmadeinthisdocumentaretrueandcorrecttothebestofhisknowledge,informationandbelief,andthatheisauthorizedtoexecutethedocumentonbehalfofsaidLicensee.J.A.StallSTATEOFFLORIDA(COUNTYOFSTC.OcteSworntoandsubscribedbeforemethis2>dayof/4dA'~I0~,19~byJ.A.Stall,whoispersonallyknowntome."SignatureofNoPublic-StateofFloridaGEORGER.teOOEg!'.r:a.=MY00MMISl0HtCC062026EXPlRES:June17,2000";p,~"BondedTtuuNotaryPuScUndeneltsaNameofNotaryPublic(Print,Type,orStamp

~'1AgHQre St.LuciqUnit1'ocketNo.50-335ProposedLicenseAmendmentCSadaeee-98-83EVALUATIONOFPROPOSEDTSCHANGES1.0Introduction2.0Background3.0ProposedChanges:DescriptionandBases/Justification3.1TS1.10:DOSEEQUIVALENTI-1313.2TSFigure2.1-1:REACTORCORETHERMALMARGINSAFETYLIMIT-FOURREACTORCOOLINGPUMPSOPERATING3.3TSTable2.2-1:REACTORPROTECTIVEINSTRUMENTATIONTRIPSETPOINTLIMITSandTSTable3.2-1:DNBMARGINLIMITS3.4BASES2.2:LIMITINGSAFETYSYSTEMSETTINGS3.5TS5.6:FUELSTORAGE3.6TS6.9.1.11:COREOPERATINGLIMITSREPORT(COLR)4.0SummaryofEvaluationofImpactfromProposedMinimumRCSFlowandLow-FlowTripSetpointonPlantAnalyses4.1EvaluationofDesignBasisEvents4.2SetpointAnalyses4.3ImpactoftheLicenseAmendmentonOtherAnalyses5.0EnvironmentalConsideration6.0Conclusion~7.0ReferencesNote:Informationinthisattachment,inpart,hasbeenreformattedandeditedfromFPLNuclearEngineeringSafetyEvaluationPSL-ENG-SEFJ-98-009:11/5/98.

St.LucieUnit1'ocketNo.50-335ProposedLicenseAmendmentCUdaeL-98-283Attachment1Page1of11EVALUATIONOFPROPOSEDTSCHANGESTheproposedamendmenttoFacilityOperatingLicenseDPR-67forSt.LucieUnit1(PSL1)willrevisetheThermalMarginSafetyLimitLinesofTechnicalSpecifications(TS)Figure2.1-1toreflectanincreaseinthevalueofdesignminimumReactorCoolantSystem(RCS)flowfrom345,000gpmto365,000gpm,andchangetheflowratesstatedinTables2.2-1and3.2-1accordingly.ThereactorprotectiveinstrumentationReactorCoolantFlow-Lowtripsetpointlimitswillbechangedfrom93%to95%ofdesignRCSflow.Theseproposedchangesareintendedtorecovertheanalysismarginlostasaresultofchangestotheflowandlow-flowtripsetpointlimitsthatweremadenecessarybysteamgeneratortubepluggingovermorethan20yearsofplantoperation.ThesteamgeneratorsatSt.LucieUnit1werereplacedduringthe1997refuelingoutageforthecurrentoperatingcycleand,duetotheresultantincreaseinRCSflow,theproposedchangeswillbenefitthesafetyanalyseswhilemaintainingsufficientoperatingmarginsrelatedtotheseparameters.Otherchangesproposedinthislicenseamendmentinclude:arevisiontoTS1.10toupdatethereferencefordoseconversionfactorsusedinDoseEquivalentIodine-131calculationsfromthoselistedinTableIIIofTID-14844tothoselistedinICRP-30;andadministrativechangesthatdeletethenumericalvalueofcriticalityanalysisuncertaintydescribedinfuelstoragedesignfeaturesTS5.6.1.a.1,updatetheanalyticalmethodsusedfordeterminingcoreoperatinglimitslistedinadministrativecontrolsTS6.9.1.11,andreviseLimitingSafetySystemSettingsBases2.2fortheSteamGeneratorPressure-Lowtriptodeletethenumericalvalueofsteampressuredescribedasthefullloadoperatingpoint.FPLhasdeterminedthattheproposedrevisionswouldnotadverselyaffectthesafetyanalysesconclusionssupportingtheoperationofSt.LucieUnit1,anditisconcludedinAttachment2thattheproposedamendmentdoesnotinvolveasignificanthazardsconsideration.20BacouTS1.10:"DOSEEQUIVALENTI-131shallbethatconcentrationofI-131(pCi/gram)whichalonewouldproducethesamethyroiddoseasthequantityandisotopicmixtureofI-131,l-132,I-133,1-134,andI-135actuallypresent.ThethyroiddoseconversionfactorsusedforthiscalculationshallbethoselistedinTableIIIofTID-14844,'CalculationofDistanceFactorsforPowerandTestReactorSites'."RCSLimitingConditionforOperationTS3.4.8,"SpecificActivity,"establisheslimitsandsurveillancerequirementsforDOSEEQUIVALENTl-131intheprimarycoolant.TheSt.LucieUnit1steamgeneratorswerereplacedin1997duringtheCycle-15refuelingoutageaftermorethan20yearsofplantoperation.RCSflowhaddecreasedconsiderablywiththeoldsteamgeneratorsasaresult,inpart,ofhavingapproximately25%(average)ofthetotalnumberoftubesplugged.RevisionstothespecifieddesignminimumRCSflowthroughtheyearsculminatedwiththecurrentlyspecifiedvalueof345,000gpm.RCSflowwiththereplacementsteamgeneratorsisgreaterthan400,000gpm.TS2.1.1requiresthat"thecombinationofTHERMALPOWER,pressurizerpressure,andmaximumcoldlegcoolanttemperatureshallnotexceedthelimitsshownonFigure2.1-1."ThecurvesofFigure St.LucieUnit1'ocketNo.50-335iProposedLicenseAmendmentCSoadSUdaeL-98-283Attachment1Page2of112.1-1representthelociofpointsfortheseparameters,withfourreactorcoolingpumpsoperating,forwhichtheminimumDeparturefromNucleateBoilingRatio(DNBR)isnolessthantheDNBRlimitfortheaxial(powerdistribution)shapeshowninFigureB2.1-1.ThepresentFigure2.1-1showsthermalmarginsafetylimitlinesthatarevalidforreactorvesselflowof345,000gpmandisannotatedaccordingly.TS2.2.1requiresthatthereactorprotectiveinstrumentationsetpointsshallbesetconsistentwiththeTripSetpointvaluesshowninTable2.2-1.ThetablepresentlyliststhetripsetpointandtheallowablevaluefortheReactorCoolantFlow-Lowtripasz93%ofdesignreactorcoolantflowwith4pumpsoperating*.Theasteriskisfootnotedwiththestatement,"*Designreactorcoolantflowwith4pumpsoperatingis345,000gpm."TS3.2.5requiresthatDNBrelatedparametersshallbemaintainedwithinthelimitsshownonTable3.2-1.Thistableliststhereactorcoolantflowrateas~345,000gpm.BASES2.2,LIMITINGSAFETYSYSTEMSETTINGSstates,"TheSteamGeneratorPressure-Lowtripprovidesprotectionagainstanexcessiverateofheatextractionfromthesteamgeneratorsandsubsequentcooldownofthereactorcoolant.Thesettingof600psiaissufficientlybelowthefull-loadoperatingpointof800psigsoasnottointerferewithnormaloperation,butstillhighenoughtoprovidetherequiredprotectionintheeventofexcessivelyhighsteamflow.Thissettingwasusedwithanuncertaintyfactorofa22psiintheaccidentanalyses."3.0oosedCaesDesc'oa8sesJustcatioTheaffectedTSpages,marked-uptoshowtheproposedchanges,areincludedinAttachment3.3.1S0ae1-3DOSEEUV-3IntheDefinitionofDOSEEQUIVALENT1-131,thereferenceforthethyroiddoseconversionfactorsischangedfrom"TableIIIofTID-14844,'CalculationofDistanceFactorsforPowerandTestReactorSites'."to"ICRP-30,SupplementtoPart1,pages192-212,Tablesentitled,'CommittedDoseEquivalentinTargetOrgansorTissuesperIntakeofUnitActivity(Sv/Bq)'."Basis/Justificatio:ThederivedlimitsintheInternationalCommissiononRadiologicalProtection(ICRP),Publication30(Reference1),representmorerecentvaluesforthethyroiddoseconversionfactors,andincorporatetheconsiderableadvancesinthestateofknowledgeoflimitsforintakesofradionuclides.TheICRPdoseconversionfactorsareconsistentwiththeFederalGuidanceReportNo.11(Reference2),andtherecommendationsofEnvironmentalProtectionAgency(EPA)1987guidance.ThesyntaxusedfortheICRP-30referenceinproposedTS1.10isconsistentwiththecorrespondingdefinitionintheStandardTSforCombustionEngineeringPlants(NUREG-1432).ThesafetyanalysesofrecorddoseconsequencesarebasedontheTID-14844thyroiddoseconversionfactors.SincethesedoseconversionfactorsproduceconservativedoseconsequencesascomparedtotheproposedchangetoICRP-30,thedoseconsequencesofalltheanalysesofrecordremainboundingfortheproposedchanges.Theanalyses St.LucieUnit1'ocketNo.50-335ProposedLicenseAmendmentCS'ulowandSUdateL-98-283Attachment1Page3of11consequencesthuswouldcontinuetoremainincompliancewiththeacceptancecriteriaof10CFR100limits,andnoreanalysisisrequired.However,theproposedchangewouldallowtheuseoftheICRPvaluesfordoseconsequencesofanyfuturereanalysis,consistentwiththecurrentindustiystandards.3.2aUSGThecurrentThermalMarginSafetyLimitLinesandthenotationofFigure2.1-1reflectadesignminimumRCSflowof345,000gpm,andarerevisedtoincludetheeffectsoftheproposeddesignreactorcoolantflowof365,000gpmwithfourpumpsoperating.Figure2.1-1isassociatedwiththeTSBasisFigureB2.1-1thatremainsunchanged.I!replacementsteamgeneratorswasapproximately407,000gpm.Theexpectedflowwithanassumedvalueof15%steamgeneratortubepluggingisinexcessof380,000gpm.TheproposedincreaseintheminimumdesignRCSflowto365,000gpmwouldthusprovidesufficientmargintoTSflowcompliancewith15%steamgeneratortubeplugging,afteraccountingfortheflowmeasurementuncertainties.TherevisedTSFigure2.1-1includestheeffectsoftheproposedreactorcoolantsystemdesignflowrateof365,000gpmwithfourreactorcoolantpumpsoperating.Thenewlimitsonplantoperatingspaceshownontheupdatedfigurewereobtainedutilizingcurrentfuelvendorapprovedmethodology,andisassociatedwiththeaxialpowerdistributionshownintheTechnicalSpecificationBasisFigureB2.1-1.TheThermalMarginSafetyLimitLinesshowninFigure2.1-1donotincludeallowancesforinstrumenterrororfluctuations.Assuch,thisfigurecannotbedirectlyusedtoverifyanytripsetpoints.ImplementationofthesesafetylimitsintheplantdoesrequireconsiderationofinstrumenterrorandotheruncertaintyeffectswhichareincludedinthegenerationoftheThermalMargin/LowPressure(TM/LP)tripandVariableHighPowerTrip(VHPT)functionsandinthepressurevaluesselectedfortheactuationofMainSteamSafetyValves.Thissetpointverificationisperformedeverycycletoconfirmtheadequacyofthetripfunctionstoprovidenecessaryplantprotection.FPLhasevaluatedtheimpactoftheproposedchangetoRCSdesignminimumflowonapplicableplantanalyses,anddeterminedthattheproposedrevisionswouldnotadverselyaffectthesafetyanalysesconclusionssupportingtheoperationofSt.LucieUnit1.TheresultsofthisevaluationaresummarizedinPart4.0ofthisattachment.3.3CO0CSUTOae-andTSTABL32-DBGIITSPae3/42-140STable2.2-1isrevisedtochangetheReactorCoolantFlow-LowTRIPSETPOINTandALLOWABLEVALUEfrom93%ofdesignreactorcoolantflowwith4pumpsoperatingto95%ofdesignreactorcoolantflowwith4pumpsoperating.Inthefootnoteatthebottomofpage2-4,thedesignreactorcoolantflowwith4pumpsoperatingischangedfrom345,000gpmto365,000gpm.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment'CSuaSUdaeL-98-283Attachment1Page4of11Table3.2-1ofTS3.2.5isrevisedtochangetheReactorCoolantFlowRatefrom>345,000gpmto>365,000gpm.RCSflowfrom345,000gpmto365,000gpm,andanincreaseintheReactorCoolantFlow-LowTRIPSETPOINTandALLOWABLEVALUESfrom93%to95%ofthedesignreactorcoolantflowwith4pumpsoperating.ThesechangeswillprovideincreasedanalysismargintotheDeparturefromNucleateBoilingRatio(DNBR),whilemaintainingsufficientoperatingmarginstotheseparametersduetothehigherRCSflowresultingfromthereplacementsteamgenerators.TheRCSflowmeasuredduringtheoperationof*Cycle15withthereplacementsteamgeneratorswasapproximately407,000gpm.Theexpectedflowwithanassumedvalueof15%steamgeneratortubepluggingisinexcessof380,000gpm.TheproposedincreaseintheminimumdesignRCSflowto365,000gpmwouldthusprovidesufficientmargintoTSflowcompliancewith15%steamgeneratortubepluggingafteraccountingfortheflowmeasurementuncertainties.Additionally,theincreaseinthelow-flowtripsetpointvalueto95%ofthedesignRCSflowwouldmaintainadequateoperationalmargintothetripsetpoint.Theseproposedvaluesarecomparabletothevaluesof370,000gpmfordesignRCSflowand95%ofdesignRCSflowforthetripsetpointthatexistedpriortothechangesthatweremadebyLicenseAmendmentNo.130toaccommodatesteamgeneratortubepluggingupto25%(average).TherevisiontoTSTable3.2-1,DNBMARGINLIMITS,isconsistentwiththereviseddesignreactorcoolantflowwith4pumpsoperating,annotatedinproposedFigure2.2-1andintheproposedfootnoteofTable2.2-1.FPLhasevaluatedtheimpactonapplicableplantanalysesfromtheproposedchangetotheReactorCoolantFlow-LowTRIPSETPOINTandALLOWABLEVALUESinconjunctionwiththeproposedRCSminimumflowvalue,anddeterminedthattheproposedrevisionswouldnotadverselyaffectthesafetyanalysesconclusionssupportingtheoperationofSt.LucieUnit1.TheresultsofthisevaluationaresummarizedinPart4.0ofthisattachment3.4SGSSSGSe-5TheBasesfor"SteamGeneratorPressure-Low"isrevisedtodeletethespecificnumericalvalueof800psigpresentlydescribedasthe"full-loadoperatingpoint."Pressure-Lowreactorprotectivesystemtripsetpointcurrentlydescribesthesteampressurefull-loadoperatingpointas800psig.TheproposedrevisionwilldeletethisnumericalvaluefromtheBases.Thepresentfull-loadoperatingpointfollowingreplacementoftheSt.LucieUnit1steamgeneratorsisapproximately850psigandwillchangeoverthelifeofthenewsteamgenerators,inpart,asafunctionofsteamgeneratortubeplugging.Thenumericalvalueofthefull-loadsteampressureiscontainedinthebasesinasimpledescriptivecontextand,assuch,hasnobearingonthedesignrequirementtohavethissetpointsufficientlybelowthefull-loadoperating

~~Q St.LuciyUnit1'ocketNo.50-335ProposedLicenseAmendmentCSuoadSUdateL-98-283Attachment1Page5of11pointsoasnottointerferewithnormalplantoperation.TheproposedchangewillnotalterthemeaningoftheaffectedBasesstatementandwillobviatetheneedforfuturelicenseamendment(s)tomaintainitsaccuracy.3.5S56'LS0AGEPae5-5TS5.6.1.a.statesthatthespentfuelstorageracksaredesignedandshallbemaintainedwith:"1.Akequivalenttolessthanorequalto0.95whenfloodedwithunboratedwater,whichincludesaconservativeallowanceof0.0065b,kforuncertainties."ThenumericalvalueforuncertaintyallowanceisdeletedandTS5.6.1.a.1isrevisedtoread:"Qlessthanorequalto0.95iffullyfloodedwithunboratedwater,whichincludesanallowanceforuncertaintiesasdescribedinSection9.1oftheUpdatedFinalSafetyAnalysisReport."allowancespecifiedinthisTS.Thefuelstoragecriticalityanalysis,however,wouldcontinuetoaccountforproperuncertaintiesandbiasesasappropriatefortheanalyticalmethodsinuse.ThereisnochangetothefuelstoragecriticalityanalysisorthecalculatedvalueofQduetothisproposedrevision.3.6ThefuelstoragecriticalityanalysisuncertaintiesarecurrentlydelineatedindetailinTable9.1-12oftheUpdatedFinalSafetyAnalysisReport(UFSAR).Sincetheuncertaintyvalueisdependentonthemethodsandassumptionsusedinthecriticalityanalysis,itisappropriateforthisvaluetobedescribedintheUFSAR.TheproposedchangeisalsoconsistentwiththeStandardTSforCombustionEngineeringPlants(NUREG-1432).Anychangestothefuelstoragecriticalityanalysisandthecorrespondinguncertaintieswillbecontrolledpursuantto10CFR50.59.aS69CO0EGS0COaes6-96-9aTheanalyticalmethodslistedinTS6.9.1.11.bareupdatedtoincludeinaconsistentmannerthecurrentfuelvendor(SiemensPowerCorporation)methodologythatisusedorcouldbeusedtodeterminetheSt.LucieUnit1coreoperatinglimitsthataredocumentedintheCoreOperatingLimitsReport(COLR).ExistingItems3through11.e)arerevisedwitheditorialcorrectionstoimproveclarityandaccuracyofreportidentification.Items6.b),11.f),and12through16areadditionstotheexistinglist.TherevisionsarepresentedasINSERT-BinAttachment3.properlyidentifytheapproved'ethodologiesusedortobeusedinthesafetyanalysesperformedfordeterminingtheSt.LucieUnit1coreoperatinglimitsthataredocumentedintheCOLR.Theupdatedlistismadeconsistentwithproperidentificationofthefuelvendor(SiemensPowerCorporation)TopicalReportsasrecommendedbythefuelvendor(Reference3)andreviewedbyFPL..Theproposedrevisiontothisspecificationisadministrativeinnature.

0~III St.LuciyUnit1DocketNo.50-335ProposedLicenseAmendmentCS'dUdaeL-98-283Attachment1Page6of11*TwooftheTopicalReportsshownintherevisedlistarecurrentlyunderreviewbytheNRCstaff.Therefore,inclusionoftheseTopicalReports(specifliedbelow)inTS6.9.1.11.biscontingentuponcompletionofthestaff'sreviewandfinalapproval.~ebb:EMF-84-093(P)Revision1,"SteamLineBreakMethodologyforPWRs,"SiemensPowerCorporation,June1998(ThisdocumentisarevisiontoANF-84-93).gee~:EMF-2087(P)Revision0,"SEM/PWR-98:ECCSEvaluationModelforPWRLBLOCAApplications,"SiemensPowerCorporation,August1998.Themethodologiesthathavebeenaddedtothelist(Item6.b),Item11.f),andItems12through16)coulddirectlyorindirectlybeusedindeterminingtheCOLRlimitsandareincludedtomakethelistcomprehensive.ThesemethodologiesincludethoseusedinperforminglargebreakLOCAanalyses,non-LOCAtransientanalysesandsetpointverificationanalyses,andthosethatsupporttheuseofgadoliniafuelandextendedburnups.4.0Suaoauat'ooSetotoaalsescoooseduCSoadLo-oTheDeparturefromNucleateBoilingRatio(DNBR)parameterissensitivetochangesincoreflowrateaswellasthevalueofcoreflowatthetimeofreactortrip.The"changesincludedinthisproposedlicenseamendmentaffecttheplantsafetyanalysesinthefollowingmanner:(a)anincreaseincoreflowratetendstoincreasethecalculatedDNBR.TheDNBRparameterisadirectindicationofavailablethermalmargin,andanincreaseinthecalculatedminimumDNBRindicatesthatthermalmarginforthecorrespondingtransienthasbeenincreased;and(b)anincreaseinthevalueoftheReactorCoolantFlow-LowtripsetpointwouldhaveabeneficialimpactonthecalculatedDNBRforcertaintransients.Theincreasedlow-flowtripsetpointwouldresultinthereactortripoccurringatahighercoreflowrateleadingtoanearlierreactortrip.TheevaluationoftheeffectsonsafetywasperformedbySiemensPowerCorporation(Reference4)andFPL,andissummarizedbelow:4.1aua'oofDes'asisventsThecurrentanalysesofrecordusethedesignreactorcoolantflowof345,000gpmandtheReactorCoolantFlow-Lowtripsetpointof93%ofdesignreactorcoolantflow.Theseanalysesalsosupporttheplantoperatingconditionsassociatedwiththereplacementsteamgeneratorsrelativetothesteamgeneratorpressure,RCSflow,reactoroutlettemperature,etal.(References5and6).AreviewofeventsdescribedintheSt.LucieUnit1UFSARwasperformedtoassesstheimpactofanincreaseintheReactorCoolantFlowRateto365,000gpm,andanincreaseintheReactorCoolantFlow-Lowtripsetpointvalueto95%ofdesignreactorcoolantflow.Basedonthisevaluationofdesignbasisevents,reanalysisisnotrequired.

St.LuciyUnit1'ocketNo.50-335ProposedLicenseAmendmentRCS'mumFlowandTSUdateL-98-283Attachment1Page7of11crease'ateoalbheSecondaSsemTheeventsinthiscategoryarecooldowneventsandareanalyzedforDNBR,fuelcenterlinemelt(CLM),shutdownmarginandradiologicalconsequences.AnincreaseinthedesignRCSflowratewouldhaveaninsignificantimpactontheCLMandshutdownmarginanalysesandwouldbebeneficialfromDNBRconsiderations.Theproposedchangesthereforewouldnotadverselyaffectfuelfailuresandsubsequentdoseconsequencesforeventsthatallowfuelfailures.ThelimitingeventforfuelfailuresanddoseconsequencesisSteamLineBreak.TheradiologicalconsequencesforeventswithnofuelfailuresaregovernedbytheTSactivitylevelsandtheprimarytosecondaryleakrates.Theseparametersremainunaffectedbytheproposedchanges.ThelimitingeventfordoseconsequencesinthiscategoryisInadvertentOpeningofaSteamGeneratorRelieforSafetyvalve.Thecurrentanalysesofrecord,therefore,wouldremainvalid.ecese'aeoalbeSecondaSseTheseeventsareboundedbytheLossofForcedReactorCoolantfloweventforDNBRandaremainlyanalyzedfortheover-pressurizationofprimaryandsecondarysystems.TheproposedRCSflowchangeswouldhaveaninsignificantimpactonthepressurerisefortheseevents.Thelimitingeventforover-pressurizationistheLossofExternalLoad.TheradiologicalconsequencesarebasedontheTSactivitylevelsandtheprimarytosecondaryleakrates.Theseparametersremainunaffectedbytheproposedchanges.ThelimitingeventfordoseconsequencesinthiscategoryisLossofNon-EmergencyACPowertoStationAuxiliaries.TheLossofNormalFeedwaterevent,analyzedforsecondarysideliquidinventory,wouldbelesssevereforthecaseofincreasedRCSflowduetothelowerinitialprimarysystemstoredenergythathastoberemovedbyboilirigoffthesecondarysideinventory.Thecurrentanalysesofrecord,therefore,wouldremainvalid.ecrease'acoCooantSseFlowTheseeventsaremainlyanalyzedforDeparturefromNucleateBoiling(DNB)considerations.SinceincreasedRCSflowandlowflowtripsetpointtendtoincreasethecalculatedDNBR,theanalysisofrecordwouldremainboundingfortheproposedchanges.edwe'sribu'aliesTheonlyeventsinthiscategoryimpactedbytheproposedchangesarethoseanalyzedrelativetoDNBR.SinceincreasedRCSflowandlowflowtripsetpointtendtoincreasethecalculatedDNBR,theanalysisofrecordwouldremainboundingfortheproposedchanges.cease'acoCoaeoTherearenoeventsinthiscategorywhichareimpactedbytheproposedchanges.

St.LuciqUnit1'ocketNo.50-335ProposedLicenseAmendmentCSuoaSUdaeL-98-283Attachment1Page8of11Decease'acoCoolatveoInadvertentopeningofaPressurizerPressureReliefvalveisanalyzedforDNBR.SinceanincreaseintheRCSflowtendstoincreasetheDNBR,thecurrentanalysisremainsboundingforthisevent.SteamGeneratorTubeRuptureisanalyzedforradiologicalconsequences.TheseconsequencesarebasedontheRCSandsecondarysystemactivitylevelsandtheprimarytosecondarybreakflow.TheactivitylevelsusedintheanalysisofrecordaretheTechnicalSpecificationsmaximumallowedactivitylevels,whichremainunchanged.Thedrivingforceforthebreakflowisthepressuredifferencebetweentheprimarysideandthesecondaryside.TheproposeddesignRCSflowratecorrespondstoasteamgeneratortubeplugginglevelofbetween15%and25%.Theprimarytosecondarypressuredifferenceattheseconditionswouldremainlowerthantheconservativepressuredifferenceusedintheanalysisofrecord,whichsupportsahighertubeplugginglevel.Adecreaseintheprimarytosecondarypressuredifferencewouldtendtoreducetheprimarytosecondarybreakflowandresultinlowerdoseconsequences.Theanalysisofrecordwouldthusremainbounding.Theincreaseincoreflowratewouldcauseasmallreductioninthecoreaveragetemperature.ThedecreasedtemperaturewouldtendtoincreasetherateofdepressurizationinthesmallbreakLOCAtransient,andeventuallyresultinadecreaseinthepeakcladdingtemperature(PCT).ThedecreasedtemperaturewouldcauseasmallchangeintheblowdowncharacteristicsofalargebreakLOCAtransient.TheeffectsofthesechangesareestimatedtobesmallwithaninsignificantimpactonthePCT.TheanalysesofrecordforsmallbreakandlargebreakLOCAswouldthusremainboundingfortheproposedchanges.ad'oacieeeasesfromaSubsseoCooenThecoreflowratehasnodirectimpactontheconsequencesofeventsinthiscategory,whichthereforeremainboundingfortheproposedchanges.4.2Thesetpointanalysesverifythefollowingsetpoints:DNB-LimitingConditionforOperation(DNB-LCO)DNB-IimitingSafetySystemSettings(DNB-LSSS)LocalPowerDensity-LimitingConditionforOperation(LPD-LCO)LocalPowerDensity-LimitingSafetySystemSettings(LPD-LSSS)IncreasesinthedesignRCSflowandthelowflowtripsetpointhavenoimpactontheLPD-LCOandLPD-LSSSverificationanalyses.SinceanincreaseintheRCSflowtendstoincreasetheDNBR,thecurrentDNB-LCOandDNB-LSSSanalyseswouldremainboundingforthecasewithincreasedRCSflowandlowflowtripsetpointvalues.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentCS'owandSUdaeL-98-283Attachment1Page9of114.3eLiceseedeo0easesWhiletheprecedingdiscussionfocusedontheimpactoftheproposedchangestotheRCSflowandthelow-flowtripsetpointontheresultsoftheplantUFSARChapter15SafetyAnalysis,acompleteevaluationoftheimpactoftheproposedchangesrequirestheevaluationofseveraladditionalissues.AdetailedevaluationofalltheseissueswasperformedforCycle15(Reference6)toaddresstheimpactoftheincreasedRCSflowduetothereplacementsteamgenerators.Theproposedchangeaffectsonlytheminimumflowanalyses.SincetheproposedchangeistoincreasetheminimumRCSflow,theimpactofthechangeremainsboundedbytheminimumandmaximumflowanalysesofrecord.Asummaryofotherimportantissuesisprovidedbelow:aaualCirculaioCaabiliNaturalcirculationcapabilityisdeterminedmainlybytheplantconfigurationparameters,whichremainunchangedbytheproposedamendment,andisnotsignificantlyimpactedbythesteadystatedesignminimumRCSflowandthelow-flowtripsetpointvalues.Theproposedchangesthuswouldnothaveanysignificantadverseimpactonthenaturalcirculationcoolingcapabilityoftheplant.eCoa'essuooBOCoSeaSsea'AchangeinthesteadystatedesignRCSflowwouldimpactthecontainmentanalysisonlythroughachangeintheinitialstoredenergy.TheproposedincreaseinthedesignRCSflowwouldcauseareductionintheRCSaveragetemperatureofabout1.5'F,andacorrespondingreductionintheinitialsystemenergy.Alowerinitialstoredenergywouldbebeneficialfromthecontainmentanalysisviewpointbecausealowerinitialstoredenergywouldresultinalowerpeakcontainmentpressure.Thepeakpressureintheanalysisofrecordwouldthusremainboundingfortheproposedchanges.eedaeseeeeaTheexistingsystemevaluationfortheAFWsystemidentifiedthiseventinconjunctionwithlossofoff-sitepowerasthelimitingconditionforplantoperatorstobeabletoinitiateauxiliaryfeedwaterflow.ThiseventisbenefitedbyadecreaseintheinitialaverageRCStemperature.SincetheproposedchangetotheRCSflowwoulddecreasetheRCSaveragetemperature,thiseventwouldnotbeadverselyimpactedbytheproposedchanges.oeeaueOerressuePoecioOPAalsisAchangeintheRCSflowwouldhavenoimpactonthemassadditionpartoftheLTOPanalysis.AnincreaseintheRCSflowwouldhoweverimpacttheenergyadditionpartoftheanalysisduetoitseffectontheheattransferratefromthesecondarysidetotheprimarysideofthesteamgenerators.WiththeproposedchangetotheRCSflow,theRCSflowwouldremainwithintherangeofcurrentlyallowedminimumandmaximumRCSflowsfortheoperationoftheplant.TheeffectoftheRCSflowontheenergyadditionpartoftheanalysisthuswouldremainboundedbytheanalysisofrecord.Otherparametersaffectingthisanalysis St.LuciyUnit1DocketNo.50-335ProposedLicenseAmendmentCS'uowandTSUdateL-98-283Attachment1Page10of11aretheRCPheatoutputandtheinitialprimangtosecondarytemperaturedifference.Theseparametersarenotimpactedbytheproposedchanges.Therefore,theproposedchangeswouldhavenosignificantadverseimpactonthisevent.0eessurePotectionnalsisInAppendix5AoftheSt.LucieUnit1UFSAR,ananalysisdocumentingthesizingoftheprimaryandsecondarysafetyvalvesispresented.Theintentofthisanalysis,whichisbasedona"worstcase"lossofloadevent,istosizethesafetyvalves.Thesafetyvalveflowratesarechosensuchthatthepeaksystempressureislessthan110%ofthedesignpressure.TheimpactoftheproposedchangesontheanalysisofrecordfortheLossofExternalLoadeventwasevaluatedandfoundtobeinsignificant(discussedinPart4.1).Thisanalysisthuswouldcontinuetoremainincompliancewiththeover-pressurizationcriteria.Therefore,itisconcludedthatpressurizersafetyvalves,mainsteamsafetyvalvesandthereactorprotectivesystemwouldcontinuetoprovideoverpressureprotectionforthesteamgeneratorsandthereactorcoolantsystemwhenconsideringtheeffectsoftheproposedchanges.oCSooSessas'sTheproposedchangetotheminimumRCSflowwouldresultinadecreaseinthecorrespondingcoreoutlettemperature.TheRCStemperaturesandflowswouldcontinuetoremainwithintherangeoftemperaturescorrespondingtothecurrentlyallowedminimumandmaximumRCSflows.Therefore,thereisnoadverseimpactonanyacceptancecriteria,andsufficientmargintostresslimitswouldcontinuetoremainavailableforallRCScomponents.5.0v'etalCosdeatoTheproposedlicenseamendmentchangesrequirementswithrespecttoinstallationoruseofafacilitycomponentlocatedwithintherestrictedareaasdefinedin10CFRPart20.Theproposedamendmentinvolvesnosignificantincreaseintheamountsandnosignificantchangeinthetypesofanyeffluentsthatmaybereleasedoffsite,andnosignificantincreaseinindividualorcumulativeoccupationalradiationexposure.FPLhasconcludedthattheproposedamendmentinvolvesnosignificanthazardsconsiderationandmeetsthecriteriaforcategoricalexclusionsetforthin10CFR51.22(c)(9)andthat,pursuantto10CFR51.22(b),anenvironmentalimpactstatementorenvironmentalassessmentneednotbepreparedinconnectionwithissuanceoftheamendment.6.0~Cocus'oTheresultsofthissafetyevaluationdemonstratethattheproposedamendmentdoesnotresultinaviolationofanysafetylimitoranalysisacceptancecriterion.Therefore,thereisnosafetyconcernassociatedwiththeproposedlicenseamendment.AsshowninAttachment2,theproposedchangesdonotinvolveasignificanthazardsconsideration.FPLconcludesthatthislicenseamendmentis,therefore,acceptablewithrespecttotheoperationofSt.LucieUnit1.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentCSi'aSUdateL-98-283Attachment1Page11of117.0~eeaces1.ICRPPublication30,PartIandSupplementtoPartI,"LimitsforIntakesofRadionuclidesbyWorkers,"AnnalsoftheICRP,Vol2,No.3/4andVol3,No.1-4,1979,PergamonPress2.FederalGuidanceReportNo.11,"LimitingValuesofRadionuclideIntakeAndAirConcentrationandDoseConversionFactorsForInhalation,Submersion,AndIngestion,"OfficeofRadiationPrograms,U.S.EnvironmentalProtectionAgency,WashingtonD.C.,19883.*LetterRIW:98:269,R.I.Wescott(SPC)toR.J.Rodriguez(FPL),"ListofSPCMethodologyforSt.LucieUnit1TechnicalSpecifications,"August4,19984.*EMF-97-044,Revision1,"St.LucieUnit1,SafetyEvaluationofanIncreaseinMinimumTechnicalSpecificationRCSFlowRateto365,000gpm,"SiemensPowerCorporation,December19975.*EMF-97-058,Revision0,"St.LucieUnit1Cycle15SafetyAnalysisReport(FSARChapter15ReviewandMechanical),"SiemensPowerCorporation,July19976.*"SteamGeneratorEquivalencyReport(SGER),Revision1,SASE-Volume2,"PreparedbyFramatomeNuclearTechnologies(FTI),June1997Note:ReferencesannotatedwithanasteriskarecurrentlyretainedbytheEngineeringNuclearFuelsGroupaspartofFPL'sNuclearEngineeringDepartmentrecords.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentCS'iuoadSUdateee 3DETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATION St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentCSuoadSUdateL-98-283Attachment2Page1of2DETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATIONDescriptioofamendmentrequest:TheproposedamendmentforSt.LucieUnit1willrevisetheThermalMarginSafetyLimitLinesofTSFigure2;1-1toreflectanincreaseinthevalueofdesignminimumReactorCoolantSystem(RCS)flowfrom345,000gpmto365,000gpm,andchangetheflowratesstatedinTables2.2-1and3.2-1accordingly.ThereactorprotectiveinstrumentationReactorCoolantFlow-Lowtripsetpointlimitswillbechangedfrom93%to95%ofdesignRCSflow.Inaddition,TS1.10willberevisedtoupdatethereferencefordoseconversionfactorsusedinDoseEquivalentIodine-131calculationsfromthoselistedinTableIIIofTID-14844tothoselistedinICRP-30;andadministrativechangesareproposedthatwilldeletethenumericalvalueofcriticalityanalysisuncertaintydescribedinfuelstoragedesignfeaturesTS5.6.1.a.1,updatetheanalyticalmethodsusedfordeterminingcoreoperatinglimitslistedinadministrativecontrolsTS6.9.1.11,andreviseLimitingSafetySystemSettingsBases2.2fortheSteamGeneratorPressure-Lowtriptodeletethenumericalvalueofsteampressuredescribedasthefullloadoperatingpoint.Pursuantto10CFR50.92,adeterminationmaybemadethataproposedlicenseamendmentinvolvesnosignificanthazardsconsiderationifoperationofthefacilityinaccordancewiththeproposedamendmentwouldnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated;or(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated;or(3)involveasignificantreductioninamarginofsafety.Eachstandardisdiscussedasfollows:(1)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.ReplacementoftheSt.LucieUnit1steamgeneratorsin1997resultedinanincreaseinRCSflow.Theproposedamendmentwouldincreasethevaluesofdesignminimumreactorcoolantflowandthe,lowflowtripsetpointpresentlystatedintheTechnicalSpecifications(TS).TheserevisionsareaccompaniedbyacorrespondingchangetotheThermalMarginSafetyLimitLinesofTSFigure2.1-1.TheRCSflowrelatedrevisionsdonotchangetheprobabilityofanypreviouslyevaluatedaccident,astheydonotimpactanyplantcomponent,structureorsystemaffectingtheaccidentinitiators.TheproposedchangeswouldcontinuetomaintainadequateoperationalmargintoTSlimitsforRCSflowandthelow-flowtripsetpoint.TheproposedchangestothethyroiddoseconversionfactorsfromTID-14844toICRP-30,fuelstorageTS5.6.1.a.1,thelistofanalyticalmethodsinTS6.9.1.11,andtheBasesforSteamGeneratorPressure-Lowtripsettinghavenorelevanceto,theaccidentinitiators,andthusdonotaffectthefrequencyofoccurrenceofpreviouslyanalyzedtransients.Additionally,therearenochangestoanyactiveplantcomponentduetotheseproposedchanges.ThesupportingevaluationofproposedTSchangesdemonstratesacceptableresultsforalltheaccidentspreviouslyanalyzed,anditisconcludedthattheradiologicalconsequenceswouldremainwithintheirestablishedacceptancecriteriawhenincludingtheeffectsofincreasedRCSflow,increasedlowflowtripsetpoint,andchangetothethyroiddoseconversionfactorsusedinthedeterminationof

St.LucioUnit1DocketNo.50-335ProposedLicenseAmendmentCS'uowandSUdateL-98-283Attachment2Page2of2doseconsequences.ProposedchangestotheBasesfortheSteamGeneratorPressure-Lowtripsetpoint,fuelstoragedesignfeatures,andthelistofanalyticalmethodsinTS6.9.1.11areadministrativeinnatureanddonotimpactcurrentsafetyanalyses.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.(2)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.ThisproposedamendmentreviseslimitingflowparameterstoderiveanalysisbenefitsfromincreasedRCSflowduetothereplacementsteamgenerators,whileassuringsafeplantoperationcommensuratewiththeproposedRCSflowandlowflowtripsetpointchanges.ThesechangesalongwiththeproposedchangestotheBasesfortheSteamGeneratorPressure-Lowtripsetpoint,doseconversionfactors,thelistofanalyticalmethodsinTS6.9.1.11,andthefuelstoragedesignfeaturesdonotrequiremodificationstotheplantconfiguration,systemsorcomponentswhichwouldcreatenewfailuremodes.,Therewouldbenochangeinthemodesofoperationoftheplant.Thedesignfunctionsofallthesafetysystemsremainunchanged.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.(3)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.TheproposedamendmentreviseslimitingflowparameterstoderiveanalysisbenefitsfromincreasedRCSflowduetothereplacementsteamgenerators,whileassuringsafeplantoperationcommensuratewiththeproposeddesignminimumRCSflowandlow-flowtripsetpointchanges.FPLhasevaluatedtheimpactoftheproposedchangesonavailablemargintotheacceptancecriteriaforSpecifiedAcceptableFuelDesignLimits(SAFDL),10CFR50.46(b)requirements,primaryandsecondaryover-pressurization,peakcontainmentpressure,potentialradioactivereleases,andexistinglimitingconditionsforoperation.WiththeproposedchangestothedesignminimumRCSflow,low-flowtripsetpoint,anddoseconversionfactors,FPLhasconcludedthattherewouldbenoadverseimpacttotheexistingsafetyanalyses.TheproposedchangestotheBasesfortheSteamGeneratorPressure-Lowtripsetpoint,thelistofanalyticalmethodsinTS6.9.1.11,andthefuelstoragedesignfeaturesareadministrativeinnature.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.BasedonthediscussionpresentedaboveandonthesupportingEvaluationofProposedTSChanges,FPLhasconcludedthatthisproposedlicenseamendmentinvolvesnosignificanthazardsconsideration.