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

CATEGORY1tREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)

SUBJECT:

Application foramendtolicenseDPR-67,revising thermalmarginSLlinesofTSFigure2.1-1toreflectincreaseinvalueofdesignminRCSflowfrom345,000gpmto365,000gpm&changeflowratesstatedinTables2.2-1&.3.2-1.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:

GeneralDistribution NOTES:jpi'rACCESSION NBR:9812010024 DOC.DATE:

98/11/22NOTARIZED:

YESFACIL:50-335 St.LuciePlant,Unit1,FloridaPower&.LightCo.AUTH.NAlrgAUTHORAFFILIATION STALL,J.A.

FloridaPower6LightCo.RECIP.NAME RECIPIENT AFFILIATION RecordsManagement Branch(Document ControlDesk)DOCKET050003352,TERECIPIENT IDCODE/NAME PD2-3LAGLEAVES,W COPIESLTTRENCL1111'ECIPIENT IDCODE/NAME PD2-3PDCOPIESLTTRENCL11INTERNAL:

ACRSNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRZB OGC/HDS3EXTERNAL:

NOAC111111111011FILECETER01EKCBNRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDR11111,1111~1U'OTETOALL"RZDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTETHTOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:

LTTR14ENCL13 4(

0FloridaPower6tLightCompany,6351S.OceanDrive,JensenBeach,FL34957November22,1998L-98-28310CFR50.90U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment CSuoadTSUdaePursuantto10CFR50.90,FloridaPower8LightCompany(FPL)requeststoamendFacilityOperating LicenseDPR-67forSt.LucieUnit1byincorporating theattachedTechnical Specifications (TS)revisions.

Theamendment willrevisetheThermalMarginSafetyLimitLinesofTSFigure2.1-1toreflectanincreaseinthevalueofdesignminimumReactorCoolantSystem(RCS)flowfrom345,000gpmto365,000gpm,andchangetheflowratesstatedinTables2.2-1and3.2-1accordingly.

Thereactorprotective instrumentation ReactorCoolantFlow-Lowtripsetpointlimitswillbechangedfrom93%to95%ofdesignRCSflow.Theseproposedchangesareintendedtorecovertheanalysismarginlostasaresultofchangestotheflowandlowflowtripsetpointlimitsthatweremadenecessary bysteamgenerator tubepluggingovermorethan20yearsofplantoperation.

Thesteamgenerators atSt.LucieUnit1werereplacedduringthe1997refueling outageforthecurrentoperating cycleand,duetotheresultant increaseinRCSflow,theproposedchangeswillbenefitthesafetyanalyseswhilemaintaining sufficient operating marginsrelatedtotheseparameters.

Otherchangesproposedinthislicenseamendment include:arevisiontoTS1.10toupdatethereference fordoseconversion factorsusedinDoseEquivalent Iodine-131 calculations fromthoselistedinTableIIIofTID-14844 tothoselistedinICRP-30;andadministrative changesthatdeletethenumerical valueofcdgcaltty analysisuncertainty described infuelstoragedesignfeaturesTS5,6.1.s.t,

/updatetheanalytical methodsusedfordetermining coreoperating limitslistedinadministrative controlsTS6.9.1.11, andreviseLimitingSafetySystemSettingsBases2.2fortheSteam Generator Pressure-Lowtriptodeletethenumerical valueofsteampressuredescnbedasthefullloadoperating point.PleasenotethattwooftheTopicalReportsshownintherevisedlistofanalytical methodsforTS6.9.1.11.b arecurrently beingreviewedbytheNRCstaff.Thereportsareidentified inPart3.6ofAttachment 1(page6of11).Including theseTopicalReportsinTS6.9.1.11.b, therefore, iscontingent

.uponcompletion ofthestaff'sreviewofbothreportsandfinalapprovalthereof.Itisrequested thattheproposedamendment, ifapproved, beissuedbyAugust15,1999.Attachment 1isanevaluation oftheproposedTSchanges.Attachment 2isthe"Determination ofNoSignificant HazardsConsideration."

Attachment 3containsacopyoftheaffectedTSpagesmarked-up toshowtheproposedchanges.pp0Cgv~V~.98i20i0024

'ii8ii222t PDRADQCK05000335PDRIanFPLGroupcompany

~es~ss St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment CSuoadaeL-98-283Page2Theproposedamendment hasbeenreviewedbytheSt.LucieFacilityReviewGroupandtheFloridaPower8LightCompanyNuclearReviewBoard.Inaccordance with10CFR50.91(b)(1),acopyoftheproposedamendment isbeingforwarded totheStateDesigneefortheStateofFlorida.Pleasecontactusifthereareanyquestions aboutthissubmittal.

Verytrulyyours,J.A.StallVicePresident St.LuciePlantJAS/RLDAttachments cc:RegionalAdministrator, RegionII,USNRC.SeniorResidentInspector, USNRC,St.LuciePlant.Mr.W.A.Passetti, FloridaDepartment ofHealthandRehabilitative Services.

1rJl

~~St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment CSuowadSUdateL-98-283Page3STATEOFFLORIDA))ss.COUNTYOFST.LUCIE)J.A.Stallbeingfirstdulysworn,deposesandsays:ThatheisVicePresident, St.LuciePlant,fortheNuclearDivisionofFloridaPower8LightCompany,theLicenseeherein;Thathehasexecutedtheforegoing document; thatthestatements madeinthisdocumentaretrueandcorrecttothebestofhisknowledge, information andbelief,andthatheisauthorized toexecutethedocumentonbehalfofsaidLicensee.

J.A.StallSTATEOFFLORIDA(COUNTYOFSTC.OcteSworntoandsubscribed beforemethis2>dayof/4dA'~I0~,19~byJ.A.Stall,whoispersonally knowntome."Signature ofNoPublic-State ofFloridaGEORGER.teOOEg!'.r:a.=MY00MMISl0H tCC062026EXPlRES:June17,2000";p,~"BondedTtuuNotaryPuSc Undeneltsa NameofNotaryPublic(Print,Type,orStamp

~'1AgHQre St.LuciqUnit1'ocketNo.50-335ProposedLicenseAmendment CSadaeee-98-83EVALUATION OFPROPOSEDTSCHANGES1.0Introduction

2.0Background

3.0ProposedChanges:Description andBases/Justification 3.1TS1.10:DOSEEQUIVALENT I-1313.2TSFigure2.1-1:REACTORCORETHERMALMARGINSAFETYLIMIT-FOUR REACTORCOOLINGPUMPSOPERATING 3.3TSTable2.2-1:REACTORPROTECTIVE INSTRUMENTATION TRIPSETPOINTLIMITSandTSTable3.2-1:DNBMARGINLIMITS3.4BASES2.2:LIMITINGSAFETYSYSTEMSETTINGS3.5TS5.6:FUELSTORAGE3.6TS6.9.1.11:

COREOPERATING LIMITSREPORT(COLR)4.0SummaryofEvaluation ofImpactfromProposedMinimumRCSFlowandLow-FlowTripSetpointonPlantAnalyses4.1Evaluation ofDesignBasisEvents4.2SetpointAnalyses4.3ImpactoftheLicenseAmendment onOtherAnalyses5.0Environmental Consideration

6.0 Conclusion

~7.0References Note:Information inthisattachment, inpart,hasbeenreformatted andeditedfromFPLNuclearEngineering SafetyEvaluation PSL-ENG-SEFJ-98-009:

11/5/98.

St.LucieUnit1'ocketNo.50-335ProposedLicenseAmendment CUdaeL-98-283Attachment 1Page1of11EVALUATION OFPROPOSEDTSCHANGESTheproposedamendment toFacilityOperating LicenseDPR-67forSt.LucieUnit1(PSL1)willrevisetheThermalMarginSafetyLimitLinesofTechnical Specifications (TS)Figure2.1-1toreflectanincreaseinthevalueofdesignminimumReactorCoolantSystem(RCS)flowfrom345,000gpmto365,000gpm,andchangetheflowratesstatedinTables2.2-1and3.2-1accordingly.

Thereactorprotective instrumentation ReactorCoolantFlow-Lowtripsetpointlimitswillbechangedfrom93%to95%ofdesignRCSflow.Theseproposedchangesareintendedtorecovertheanalysismarginlostasaresultofchangestotheflowandlow-flowtripsetpointlimitsthatweremadenecessary bysteamgenerator tubepluggingovermorethan20yearsofplantoperation.

Thesteamgenerators atSt.LucieUnit1werereplacedduringthe1997refueling outageforthecurrentoperating cycleand,duetotheresultant increaseinRCSflow,theproposedchangeswillbenefitthesafetyanalyseswhilemaintaining sufficient operating marginsrelatedtotheseparameters.

Otherchangesproposedinthislicenseamendment include:arevisiontoTS1.10toupdatethereference fordoseconversion factorsusedinDoseEquivalent Iodine-131 calculations fromthoselistedinTableIIIofTID-14844 tothoselistedinICRP-30;andadministrative changesthatdeletethenumerical valueofcriticality analysisuncertainty described infuelstoragedesignfeaturesTS5.6.1.a.1, updatetheanalytical methodsusedfordetermining coreoperating limitslistedinadministrative controlsTS6.9.1.11, andreviseLimitingSafetySystemSettingsBases2.2fortheSteamGenerator Pressure-Lowtriptodeletethenumerical valueofsteampressuredescribed asthefullloadoperating point.FPLhasdetermined thattheproposedrevisions wouldnotadversely affectthesafetyanalysesconclusions supporting theoperation ofSt.LucieUnit1,anditisconcluded inAttachment 2thattheproposedamendment doesnotinvolveasignificant hazardsconsideration.

20BacouTS1.10:"DOSEEQUIVALENT I-131shallbethatconcentration ofI-131(pCi/gram) whichalonewouldproducethesamethyroiddoseasthequantityandisotopicmixtureofI-131,l-132,I-133,1-134,andI-135actuallypresent.Thethyroiddoseconversion factorsusedforthiscalculation shallbethoselistedinTableIIIofTID-14844,

'Calculation ofDistanceFactorsforPowerandTestReactorSites'."RCSLimitingCondition forOperation TS3.4.8,"Specific Activity,"

establishes limitsandsurveillance requirements forDOSEEQUIVALENT l-131intheprimarycoolant.TheSt.LucieUnit1steamgenerators werereplacedin1997duringtheCycle-15refueling outageaftermorethan20yearsofplantoperation.

RCSflowhaddecreased considerably withtheoldsteamgenerators asaresult,inpart,ofhavingapproximately 25%(average) ofthetotalnumberoftubesplugged.Revisions tothespecified designminimumRCSflowthroughtheyearsculminated withthecurrently specified valueof345,000gpm.RCSflowwiththereplacement steamgenerators isgreaterthan400,000gpm.TS2.1.1requiresthat"thecombination ofTHERMALPOWER,pressurizer

pressure, andmaximumcoldlegcoolanttemperature shallnotexceedthelimitsshownonFigure2.1-1."ThecurvesofFigure St.LucieUnit1'ocketNo.50-335iProposedLicenseAmendment CSoadSUdaeL-98-283Attachment 1Page2of112.1-1represent thelociofpointsfortheseparameters, withfourreactorcoolingpumpsoperating, forwhichtheminimumDeparture fromNucleateBoilingRatio(DNBR)isnolessthantheDNBRlimitfortheaxial(powerdistribution) shapeshowninFigureB2.1-1.ThepresentFigure2.1-1showsthermalmarginsafetylimitlinesthatarevalidforreactorvesselflowof345,000gpmandisannotated accordingly.

TS2.2.1requiresthatthereactorprotective instrumentation setpoints shallbesetconsistent withtheTripSetpointvaluesshowninTable2.2-1.Thetablepresently liststhetripsetpointandtheallowable valuefortheReactorCoolantFlow-Lowtripasz93%ofdesignreactorcoolantflowwith4pumpsoperating*.

Theasteriskisfootnoted withthestatement,

"*Designreactorcoolantflowwith4pumpsoperating is345,000gpm."TS3.2.5requiresthatDNBrelatedparameters shallbemaintained withinthelimitsshownonTable3.2-1.Thistableliststhereactorcoolantflowrateas~345,000gpm.BASES2.2,LIMITINGSAFETYSYSTEMSETTINGSstates,"TheSteamGenerator Pressure-Low tripprovidesprotection againstanexcessive rateofheatextraction fromthesteamgenerators andsubsequent cooldownofthereactorcoolant.Thesettingof600psiaissufficiently belowthefull-load operating pointof800psigsoasnottointerfere withnormaloperation, butstillhighenoughtoprovidetherequiredprotection intheeventofexcessively highsteamflow.Thissettingwasusedwithanuncertainty factorofa22psiintheaccidentanalyses."

3.0oosedCaesDesc'oa8sesJustcatioTheaffectedTSpages,marked-up toshowtheproposedchanges,areincludedinAttachment 3.3.1S0ae1-3DOSEEUV-3IntheDefinition ofDOSEEQUIVALENT 1-131,thereference forthethyroiddoseconversion factorsischangedfrom"TableIIIofTID-14844,

'Calculation ofDistanceFactorsforPowerandTestReactorSites'."to"ICRP-30, Supplement toPart1,pages192-212,Tablesentitled,

'Committed DoseEquivalent inTargetOrgansorTissuesperIntakeofUnitActivity(Sv/Bq)'."

Basis/Justificatio:

ThederivedlimitsintheInternational Commission onRadiological Protection (ICRP),Publication 30(Reference 1),represent morerecentvaluesforthethyroiddoseconversion factors,andincorporate theconsiderable advancesinthestateofknowledge oflimitsforintakesofradionuclides.

TheICRPdoseconversion factorsareconsistent withtheFederalGuidanceReportNo.11(Reference 2),andtherecommendations ofEnvironmental Protection Agency(EPA)1987guidance.

ThesyntaxusedfortheICRP-30reference inproposedTS1.10isconsistent withthecorresponding definition intheStandardTSforCombustion Engineering Plants(NUREG-1432).

Thesafetyanalysesofrecorddoseconsequences arebasedontheTID-14844 thyroiddoseconversion factors.Sincethesedoseconversion factorsproduceconservative doseconsequences ascomparedtotheproposedchangetoICRP-30,thedoseconsequences ofalltheanalysesofrecordremainboundingfortheproposedchanges.Theanalyses St.LucieUnit1'ocketNo.50-335ProposedLicenseAmendment CS'ulowandSUdateL-98-283Attachment 1Page3of11consequences thuswouldcontinuetoremainincompliance withtheacceptance criteriaof10CFR100limits,andnoreanalysis isrequired.

However,theproposedchangewouldallowtheuseoftheICRPvaluesfordoseconsequences ofanyfuturereanalysis, consistent withthecurrentindustiystandards.

3.2aUSGThecurrentThermalMarginSafetyLimitLinesandthenotationofFigure2.1-1reflectadesignminimumRCSflowof345,000gpm,andarerevisedtoincludetheeffectsoftheproposeddesignreactorcoolantflowof365,000gpmwithfourpumpsoperating.

Figure2.1-1isassociated withtheTSBasisFigureB2.1-1thatremainsunchanged.

I!replacement steamgenerators wasapproximately 407,000gpm.Theexpectedflowwithanassumedvalueof15%steamgenerator tubepluggingisinexcessof380,000gpm.TheproposedincreaseintheminimumdesignRCSflowto365,000gpmwouldthusprovidesufficient margintoTSflowcompliance with15%steamgenerator tubeplugging, afteraccounting fortheflowmeasurement uncertainties.

TherevisedTSFigure2.1-1includestheeffectsoftheproposedreactorcoolantsystemdesignflowrateof365,000gpmwithfourreactorcoolantpumpsoperating.

Thenewlimitsonplantoperating spaceshownontheupdatedfigurewereobtainedutilizing currentfuelvendorapprovedmethodology, andisassociated withtheaxialpowerdistribution shownintheTechnical Specification BasisFigureB2.1-1.TheThermalMarginSafetyLimitLinesshowninFigure2.1-1donotincludeallowances forinstrument errororfluctuations.

Assuch,thisfigurecannotbedirectlyusedtoverifyanytripsetpoints.

Implementation ofthesesafetylimitsintheplantdoesrequireconsideration ofinstrument errorandotheruncertainty effectswhichareincludedinthegeneration oftheThermalMargin/Low Pressure(TM/LP)tripandVariableHighPowerTrip(VHPT)functions andinthepressurevaluesselectedfortheactuation ofMainSteamSafetyValves.Thissetpointverification isperformed everycycletoconfirmtheadequacyofthetripfunctions toprovidenecessary plantprotection.

FPLhasevaluated theimpactoftheproposedchangetoRCSdesignminimumflowonapplicable plantanalyses, anddetermined thattheproposedrevisions wouldnotadversely affectthesafetyanalysesconclusions supporting theoperation ofSt.LucieUnit1.Theresultsofthisevaluation aresummarized inPart4.0ofthisattachment.

3.3CO0CSUTOae-andTSTABL 32-DBGIITSPae3/42-140STable2.2-1isrevisedtochangetheReactorCoolantFlow-LowTRIPSETPOINTandALLOWABLE VALUEfrom93%ofdesignreactorcoolantflowwith4pumpsoperating to95%ofdesignreactorcoolantflowwith4pumpsoperating.

Inthefootnoteatthebottomofpage2-4,thedesignreactorcoolantflowwith4pumpsoperating ischangedfrom345,000gpmto365,000gpm.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment

'CSuaSUdaeL-98-283Attachment 1Page4of11Table3.2-1ofTS3.2.5isrevisedtochangetheReactorCoolantFlowRatefrom>345,000gpmto>365,000gpm.RCSflowfrom345,000gpmto365,000gpm,andanincreaseintheReactorCoolantFlow-LowTRIPSETPOINTandALLOWABLE VALUESfrom93%to95%ofthedesignreactorcoolantflowwith4pumpsoperating.

Thesechangeswillprovideincreased analysismargintotheDeparture fromNucleateBoilingRatio(DNBR),whilemaintaining sufficient operating marginstotheseparameters duetothehigherRCSflowresulting fromthereplacement steamgenerators.

TheRCSflowmeasuredduringtheoperation of*Cycle15withthereplacement steamgenerators wasapproximately 407,000gpm.Theexpectedflowwithanassumedvalueof15%steamgenerator tubepluggingisinexcessof380,000gpm.TheproposedincreaseintheminimumdesignRCSflowto365,000gpmwouldthusprovidesufficient margintoTSflowcompliance with15%steamgenerator tubepluggingafteraccounting fortheflowmeasurement uncertainties.

Additionally, theincreaseinthelow-flowtripsetpointvalueto95%ofthedesignRCSflowwouldmaintainadequateoperational margintothetripsetpoint.

Theseproposedvaluesarecomparable tothevaluesof370,000gpmfordesignRCSflowand95%ofdesignRCSflowforthetripsetpointthatexistedpriortothechangesthatweremadebyLicenseAmendment No.130toaccommodate steamgenerator tubepluggingupto25%(average).

TherevisiontoTSTable3.2-1,DNBMARGINLIMITS,isconsistent withthereviseddesignreactorcoolantflowwith4pumpsoperating, annotated inproposedFigure2.2-1andintheproposedfootnoteofTable2.2-1.FPLhasevaluated theimpactonapplicable plantanalysesfromtheproposedchangetotheReactorCoolantFlow-LowTRIPSETPOINTandALLOWABLE VALUESinconjunction withtheproposedRCSminimumflowvalue,anddetermined thattheproposedrevisions wouldnotadversely affectthesafetyanalysesconclusions supporting theoperation ofSt.LucieUnit1.Theresultsofthisevaluation aresummarized inPart4.0ofthisattachment 3.4SGSSSGSe-5TheBasesfor"SteamGenerator Pressure-Low" isrevisedtodeletethespecificnumerical valueof800psigpresently described asthe"full-load operating point."Pressure-Low reactorprotective systemtripsetpointcurrently describes thesteampressurefull-loadoperating pointas800psig.Theproposedrevisionwilldeletethisnumerical valuefromtheBases.Thepresentfull-load operating pointfollowing replacement oftheSt.LucieUnit1steamgenerators isapproximately 850psigandwillchangeoverthelifeofthenewsteamgenerators, inpart,asafunctionofsteamgenerator tubeplugging.

Thenumerical valueofthefull-load steampressureiscontained inthebasesinasimpledescriptive contextand,assuch,hasnobearingonthedesignrequirement tohavethissetpointsufficiently belowthefull-load operating

~~Q St.LuciyUnit1'ocketNo.50-335ProposedLicenseAmendment CSuoadSUdateL-98-283Attachment 1Page5of11pointsoasnottointerfere withnormalplantoperation.

TheproposedchangewillnotalterthemeaningoftheaffectedBasesstatement andwillobviatetheneedforfuturelicenseamendment(s) tomaintainitsaccuracy.

3.5S56'LS0AGEPae5-5TS5.6.1.a.statesthatthespentfuelstorageracksaredesignedandshallbemaintained with:"1.Akequivalent tolessthanorequalto0.95whenfloodedwithunborated water,whichincludesaconservative allowance of0.0065b,kforuncertainties."

Thenumerical valueforuncertainty allowance isdeletedandTS5.6.1.a.1 isrevisedtoread:"Qlessthanorequalto0.95iffullyfloodedwithunborated water,whichincludesanallowance foruncertainties asdescribed inSection9.1oftheUpdatedFinalSafetyAnalysisReport."allowance specified inthisTS.Thefuelstoragecriticality

analysis, however,wouldcontinuetoaccountforproperuncertainties andbiasesasappropriate fortheanalytical methodsinuse.Thereisnochangetothefuelstoragecriticality analysisorthecalculated valueofQduetothisproposedrevision.

3.6Thefuelstoragecriticality analysisuncertainties arecurrently delineated indetailinTable9.1-12oftheUpdatedFinalSafetyAnalysisReport(UFSAR).Sincetheuncertainty valueisdependent onthemethodsandassumptions usedinthecriticality

analysis, itisappropriate forthisvaluetobedescribed intheUFSAR.Theproposedchangeisalsoconsistent withtheStandardTSforCombustion Engineering Plants(NUREG-1432).

Anychangestothefuelstoragecriticality analysisandthecorresponding uncertainties willbecontrolled pursuantto10CFR50.59.aS69CO0EGS0COaes6-96-9a Theanalytical methodslistedinTS6.9.1.11.b areupdatedtoincludeinaconsistent mannerthecurrentfuelvendor(SiemensPowerCorporation) methodology thatisusedorcouldbeusedtodetermine theSt.LucieUnit1coreoperating limitsthataredocumented intheCoreOperating LimitsReport(COLR).ExistingItems3through11.e)arerevisedwitheditorial corrections toimproveclarityandaccuracyofreportidentification.

Items6.b),11.f),and12through16areadditions totheexistinglist.Therevisions arepresented asINSERT-BinAttachment 3.properlyidentifytheapproved'ethodologies usedortobeusedinthesafetyanalysesperformed fordetermining theSt.LucieUnit1coreoperating limitsthataredocumented intheCOLR.Theupdatedlistismadeconsistent withproperidentification ofthefuelvendor(SiemensPowerCorporation)

TopicalReportsasrecommended bythefuelvendor(Reference 3)andreviewedbyFPL..Theproposedrevisiontothisspecification isadministrative innature.

0~III St.LuciyUnit1DocketNo.50-335ProposedLicenseAmendment CS'dUdaeL-98-283Attachment 1Page6of11*TwooftheTopicalReportsshownintherevisedlistarecurrently underreviewbytheNRCstaff.Therefore, inclusion oftheseTopicalReports(speciflied below)inTS6.9.1.11.b iscontingent uponcompletion ofthestaff'sreviewandfinalapproval.

~ebb:EMF-84-093(P)

Revision1,"SteamLineBreakMethodology forPWRs,"SiemensPowerCorporation, June1998(ThisdocumentisarevisiontoANF-84-93).gee~:EMF-2087(P)

Revision0,"SEM/PWR-98:

ECCSEvaluation ModelforPWRLBLOCAApplications,"

SiemensPowerCorporation, August1998.Themethodologies thathavebeenaddedtothelist(Item6.b),Item11.f),andItems12through16)coulddirectlyorindirectly beusedindetermining theCOLRlimitsandareincludedtomakethelistcomprehensive.

Thesemethodologies includethoseusedinperforming largebreakLOCAanalyses, non-LOCAtransient analysesandsetpointverification

analyses, andthosethatsupporttheuseofgadolinia fuelandextendedburnups.4.0Suaoauat'ooSetotoaalsescoooseduCSoadLo-oTheDeparture fromNucleateBoilingRatio(DNBR)parameter issensitive tochangesincoreflowrateaswellasthevalueofcoreflowatthetimeofreactortrip.The"changes includedinthisproposedlicenseamendment affecttheplantsafetyanalysesinthefollowing manner:(a)anincreaseincoreflowratetendstoincreasethecalculated DNBR.TheDNBRparameter isadirectindication ofavailable thermalmargin,andanincreaseinthecalculated minimumDNBRindicates thatthermalmarginforthecorresponding transient hasbeenincreased; and(b)anincreaseinthevalueoftheReactorCoolantFlow-Lowtripsetpointwouldhaveabeneficial impactonthecalculated DNBRforcertaintransients.

Theincreased low-flowtripsetpointwouldresultinthereactortripoccurring atahighercoreflowrateleadingtoanearlierreactortrip.Theevaluation oftheeffectsonsafetywasperformed bySiemensPowerCorporation (Reference 4)andFPL,andissummarized below:4.1aua'oofDes'asisventsThecurrentanalysesofrecordusethedesignreactorcoolantflowof345,000gpmandtheReactorCoolantFlow-Lowtripsetpointof93%ofdesignreactorcoolantflow.Theseanalysesalsosupporttheplantoperating conditions associated withthereplacement steamgenerators relativetothesteamgenerator

pressure, RCSflow,reactoroutlettemperature, etal.(References 5and6).Areviewofeventsdescribed intheSt.LucieUnit1UFSARwasperformed toassesstheimpactofanincreaseintheReactorCoolantFlowRateto365,000gpm,andanincreaseintheReactorCoolantFlow-Lowtripsetpointvalueto95%ofdesignreactorcoolantflow.Basedonthisevaluation ofdesignbasisevents,reanalysis isnotrequired.

St.LuciyUnit1'ocketNo.50-335ProposedLicenseAmendment RCS'mumFlowandTS UdateL-98-283Attachment 1Page7of11crease'ateoalbheSecondaSsemTheeventsinthiscategoryarecooldowneventsandareanalyzedforDNBR,fuelcenterline melt(CLM),shutdownmarginandradiological consequences.

AnincreaseinthedesignRCSflowratewouldhaveaninsignificant impactontheCLMandshutdownmarginanalysesandwouldbebeneficial fromDNBRconsiderations.

Theproposedchangestherefore wouldnotadversely affectfuelfailuresandsubsequent doseconsequences foreventsthatallowfuelfailures.

Thelimitingeventforfuelfailuresanddoseconsequences isSteamLineBreak.Theradiological consequences foreventswithnofuelfailuresaregovernedbytheTSactivitylevelsandtheprimarytosecondary leakrates.Theseparameters remainunaffected bytheproposedchanges.Thelimitingeventfordoseconsequences inthiscategoryisInadvertent OpeningofaSteamGenerator RelieforSafetyvalve.Thecurrentanalysesofrecord,therefore, wouldremainvalid.ecese'aeoalbeSecondaSseTheseeventsareboundedbytheLossofForcedReactorCoolantfloweventforDNBRandaremainlyanalyzedfortheover-pressurization ofprimaryandsecondary systems.TheproposedRCSflowchangeswouldhaveaninsignificant impactonthepressurerisefortheseevents.Thelimitingeventforover-pressurization istheLossofExternalLoad.Theradiological consequences arebasedontheTSactivitylevelsandtheprimarytosecondary leakrates.Theseparameters remainunaffected bytheproposedchanges.Thelimitingeventfordoseconsequences inthiscategoryisLossofNon-Emergency ACPowertoStationAuxiliaries.

TheLossofNormalFeedwater event,analyzedforsecondary sideliquidinventory, wouldbelesssevereforthecaseofincreased RCSflowduetothelowerinitialprimarysystemstoredenergythathastoberemovedbyboilirigoffthesecondary sideinventory.

Thecurrentanalysesofrecord,therefore, wouldremainvalid.ecrease'acoCooantSseFlowTheseeventsaremainlyanalyzedforDeparture fromNucleateBoiling(DNB)considerations.

Sinceincreased RCSflowandlowflowtripsetpointtendtoincreasethecalculated DNBR,theanalysisofrecordwouldremainboundingfortheproposedchanges.edwe'sribu'aliesTheonlyeventsinthiscategoryimpactedbytheproposedchangesarethoseanalyzedrelativetoDNBR.Sinceincreased RCSflowandlowflowtripsetpointtendtoincreasethecalculated DNBR,theanalysisofrecordwouldremainboundingfortheproposedchanges.cease'aco CoaeoTherearenoeventsinthiscategorywhichareimpactedbytheproposedchanges.

St.LuciqUnit1'ocketNo.50-335ProposedLicenseAmendment CSuoaSUdaeL-98-283Attachment 1Page8of11Decease'acoCoolatveoInadvertent openingofaPressurizer PressureReliefvalveisanalyzedforDNBR.SinceanincreaseintheRCSflowtendstoincreasetheDNBR,thecurrentanalysisremainsboundingforthisevent.SteamGenerator TubeRuptureisanalyzedforradiological consequences.

Theseconsequences arebasedontheRCSandsecondary systemactivitylevelsandtheprimarytosecondary breakflow.TheactivitylevelsusedintheanalysisofrecordaretheTechnical Specifications maximumallowedactivitylevels,whichremainunchanged.

Thedrivingforceforthebreakflowisthepressuredifference betweentheprimarysideandthesecondary side.TheproposeddesignRCSflowratecorresponds toasteamgenerator tubeplugginglevelofbetween15%and25%.Theprimarytosecondary pressuredifference attheseconditions wouldremainlowerthantheconservative pressuredifference usedintheanalysisofrecord,whichsupportsahighertubeplugginglevel.Adecreaseintheprimarytosecondary pressuredifference wouldtendtoreducetheprimarytosecondary breakflowandresultinlowerdoseconsequences.

Theanalysisofrecordwouldthusremainbounding.

Theincreaseincoreflowratewouldcauseasmallreduction inthecoreaveragetemperature.

Thedecreased temperature wouldtendtoincreasetherateofdepressurization inthesmallbreakLOCAtransient, andeventually resultinadecreaseinthepeakcladdingtemperature (PCT).Thedecreased temperature wouldcauseasmallchangeintheblowdowncharacteristics ofalargebreakLOCAtransient.

Theeffectsofthesechangesareestimated tobesmallwithaninsignificant impactonthePCT.TheanalysesofrecordforsmallbreakandlargebreakLOCAswouldthusremainboundingfortheproposedchanges.ad'oacieeeasesfromaSubsseoCooenThecoreflowratehasnodirectimpactontheconsequences ofeventsinthiscategory, whichtherefore remainboundingfortheproposedchanges.4.2Thesetpointanalysesverifythefollowing setpoints:

DNB-Limiting Condition forOperation (DNB-LCO)

DNB-IimitingSafetySystemSettings(DNB-LSSS)

LocalPowerDensity-Limiting Condition forOperation (LPD-LCO)

LocalPowerDensity-Limiting SafetySystemSettings(LPD-LSSS)

Increases inthedesignRCSflowandthelowflowtripsetpointhavenoimpactontheLPD-LCOandLPD-LSSSverification analyses.

SinceanincreaseintheRCSflowtendstoincreasetheDNBR,thecurrentDNB-LCOandDNB-LSSSanalyseswouldremainboundingforthecasewithincreased RCSflowandlowflowtripsetpointvalues.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment CS'owandSUdaeL-98-283Attachment 1Page9of114.3eLiceseedeo0easesWhilethepreceding discussion focusedontheimpactoftheproposedchangestotheRCSflowandthelow-flowtripsetpointontheresultsoftheplantUFSARChapter15SafetyAnalysis, acompleteevaluation oftheimpactoftheproposedchangesrequirestheevaluation ofseveraladditional issues.Adetailedevaluation ofalltheseissueswasperformed forCycle15(Reference 6)toaddresstheimpactoftheincreased RCSflowduetothereplacement steamgenerators.

Theproposedchangeaffectsonlytheminimumflowanalyses.

SincetheproposedchangeistoincreasetheminimumRCSflow,theimpactofthechangeremainsboundedbytheminimumandmaximumflowanalysesofrecord.Asummaryofotherimportant issuesisprovidedbelow:aaualCirculaioCaabiliNaturalcirculation capability isdetermined mainlybytheplantconfiguration parameters, whichremainunchanged bytheproposedamendment, andisnotsignificantly impactedbythesteadystatedesignminimumRCSflowandthelow-flowtripsetpointvalues.Theproposedchangesthuswouldnothaveanysignificant adverseimpactonthenaturalcirculation coolingcapability oftheplant.eCoa'essuooBOCoSeaSsea'AchangeinthesteadystatedesignRCSflowwouldimpactthecontainment analysisonlythroughachangeintheinitialstoredenergy.TheproposedincreaseinthedesignRCSflowwouldcauseareduction intheRCSaveragetemperature ofabout1.5'F,andacorresponding reduction intheinitialsystemenergy.Alowerinitialstoredenergywouldbebeneficial fromthecontainment analysisviewpoint becausealowerinitialstoredenergywouldresultinalowerpeakcontainment pressure.

Thepeakpressureintheanalysisofrecordwouldthusremainboundingfortheproposedchanges.eedaeseeeeaTheexistingsystemevaluation fortheAFWsystemidentified thiseventinconjunction withlossofoff-sitepowerasthelimitingcondition forplantoperators tobeabletoinitiateauxiliary feedwater flow.Thiseventisbenefited byadecreaseintheinitialaverageRCStemperature.

SincetheproposedchangetotheRCSflowwoulddecreasetheRCSaveragetemperature, thiseventwouldnotbeadversely impactedbytheproposedchanges.oeeaueOerressuePoecio OPAalsisAchangeintheRCSflowwouldhavenoimpactonthemassadditionpartoftheLTOPanalysis.

AnincreaseintheRCSflowwouldhoweverimpacttheenergyadditionpartoftheanalysisduetoitseffectontheheattransferratefromthesecondary sidetotheprimarysideofthesteamgenerators.

WiththeproposedchangetotheRCSflow,theRCSflowwouldremainwithintherangeofcurrently allowedminimumandmaximumRCSflowsfortheoperation oftheplant.TheeffectoftheRCSflowontheenergyadditionpartoftheanalysisthuswouldremainboundedbytheanalysisofrecord.Otherparameters affecting thisanalysis St.LuciyUnit1DocketNo.50-335ProposedLicenseAmendment CS'uowandTSUdateL-98-283Attachment 1Page10of11aretheRCPheatoutputandtheinitialprimangtosecondary temperature difference.

Theseparameters arenotimpactedbytheproposedchanges.Therefore, theproposedchangeswouldhavenosignificant adverseimpactonthisevent.0eessurePotectionnalsisInAppendix5AoftheSt.LucieUnit1UFSAR,ananalysisdocumenting thesizingoftheprimaryandsecondary safetyvalvesispresented.

Theintentofthisanalysis, whichisbasedona"worstcase"lossofloadevent,istosizethesafetyvalves.Thesafetyvalveflowratesarechosensuchthatthepeaksystempressureislessthan110%ofthedesignpressure.

TheimpactoftheproposedchangesontheanalysisofrecordfortheLossofExternalLoadeventwasevaluated andfoundtobeinsignificant (discussed inPart4.1).Thisanalysisthuswouldcontinuetoremainincompliance withtheover-pressurization criteria.

Therefore, itisconcluded thatpressurizer safetyvalves,mainsteamsafetyvalvesandthereactorprotective systemwouldcontinuetoprovideoverpressure protection forthesteamgenerators andthereactorcoolantsystemwhenconsidering theeffectsoftheproposedchanges.oCSooSessas'sTheproposedchangetotheminimumRCSflowwouldresultinadecreaseinthecorresponding coreoutlettemperature.

TheRCStemperatures andflowswouldcontinuetoremainwithintherangeoftemperatures corresponding tothecurrently allowedminimumandmaximumRCSflows.Therefore, thereisnoadverseimpactonanyacceptance

criteria, andsufficient margintostresslimitswouldcontinuetoremainavailable forallRCScomponents.

5.0v'etalCosdeatoTheproposedlicenseamendment changesrequirements withrespecttoinstallation oruseofafacilitycomponent locatedwithintherestricted areaasdefinedin10CFRPart20.Theproposedamendment involvesnosignificant increaseintheamountsandnosignificant changeinthetypesofanyeffluents thatmaybereleasedoffsite,andnosignificant increaseinindividual orcumulative occupational radiation exposure.

FPLhasconcluded thattheproposedamendment involvesnosignificant hazardsconsideration andmeetsthecriteriaforcategorical exclusion setforthin10CFR51.22(c)(9) andthat,pursuantto10CFR51.22(b),

anenvironmental impactstatement orenvironmental assessment neednotbepreparedinconnection withissuanceoftheamendment.

6.0~Cocus'oTheresultsofthissafetyevaluation demonstrate thattheproposedamendment doesnotresultinaviolation ofanysafetylimitoranalysisacceptance criterion.

Therefore, thereisnosafetyconcernassociated withtheproposedlicenseamendment.

AsshowninAttachment 2,theproposedchangesdonotinvolveasignificant hazardsconsideration.

FPLconcludes thatthislicenseamendment is,therefore, acceptable withrespecttotheoperation ofSt.LucieUnit1.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment CSi'aSUdateL-98-283Attachment 1Page11of117.0~eeaces1.ICRPPublication 30,PartIandSupplement toPartI,"LimitsforIntakesofRadionuclides byWorkers,"Annals oftheICRP,Vol2,No.3/4andVol3,No.1-4,1979,PergamonPress2.FederalGuidanceReportNo.11,"Limiting ValuesofRadionuclide IntakeAndAirConcentration andDoseConversion FactorsForInhalation, Submersion, AndIngestion,"

OfficeofRadiation

Programs, U.S.Environmental Protection Agency,Washington D.C.,19883.*LetterRIW:98:269, R.I.Wescott(SPC)toR.J.Rodriguez (FPL),"ListofSPCMethodology forSt.LucieUnit1Technical Specifications,"

August4,19984.*EMF-97-044, Revision1,"St.LucieUnit1,SafetyEvaluation ofanIncreaseinMinimumTechnical Specification RCSFlowRateto365,000gpm,"SiemensPowerCorporation, December19975.*EMF-97-058, Revision0,"St.LucieUnit1Cycle15SafetyAnalysisReport(FSARChapter15ReviewandMechanical),"

SiemensPowerCorporation, July19976.*"SteamGenerator Equivalency Report(SGER),Revision1,SASE-Volume2,"PreparedbyFramatome NuclearTechnologies (FTI),June1997Note:References annotated withanasteriskarecurrently retainedbytheEngineering NuclearFuelsGroupaspartofFPL'sNuclearEngineering Department records.

St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment CS'iuoadSUdateee-9-3DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment CSuoadSUdateL-98-283Attachment 2Page1of2DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION Descriptio ofamendment request:Theproposedamendment forSt.LucieUnit1willrevisetheThermalMarginSafetyLimitLinesofTSFigure2;1-1toreflectanincreaseinthevalueofdesignminimumReactorCoolantSystem(RCS)flowfrom345,000gpmto365,000gpm,andchangetheflowratesstatedinTables2.2-1and3.2-1accordingly.

Thereactorprotective instrumentation ReactorCoolantFlow-Lowtripsetpointlimitswillbechangedfrom93%to95%ofdesignRCSflow.Inaddition, TS1.10willberevisedtoupdatethereference fordoseconversion factorsusedinDoseEquivalent Iodine-131 calculations fromthoselistedinTableIIIofTID-14844 tothoselistedinICRP-30;andadministrative changesareproposedthatwilldeletethenumerical valueofcriticality analysisuncertainty described infuelstoragedesignfeaturesTS5.6.1.a.1, updatetheanalytical methodsusedfordetermining coreoperating limitslistedinadministrative controlsTS6.9.1.11, andreviseLimitingSafetySystemSettingsBases2.2fortheSteamGenerator Pressure-Low triptodeletethenumerical valueofsteampressuredescribed asthefullloadoperating point.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.

Replacement oftheSt.LucieUnit1steamgenerators in1997resultedinanincreaseinRCSflow.Theproposedamendment wouldincreasethevaluesofdesignminimumreactorcoolantflowandthe,lowflowtripsetpointpresently statedintheTechnical Specifications (TS).Theserevisions areaccompanied byacorresponding changetotheThermalMarginSafetyLimitLinesofTSFigure2.1-1.TheRCSflowrelatedrevisions donotchangetheprobability ofanypreviously evaluated

accident, astheydonotimpactanyplantcomponent, structure orsystemaffecting theaccidentinitiators.

Theproposedchangeswouldcontinuetomaintainadequateoperational margintoTSlimitsforRCSflowandthelow-flowtripsetpoint.

Theproposedchangestothethyroiddoseconversion factorsfromTID-14844 toICRP-30,fuelstorageTS5.6.1.a.1, thelistofanalytical methodsinTS6.9.1.11, andtheBasesforSteamGenerator Pressure-Low tripsettinghavenorelevance to,theaccidentinitiators, andthusdonotaffectthefrequency ofoccurrence ofpreviously analyzedtransients.

Additionally, therearenochangestoanyactiveplantcomponent duetotheseproposedchanges.Thesupporting evaluation ofproposedTSchangesdemonstrates acceptable resultsforalltheaccidents previously

analyzed, anditisconcluded thattheradiological consequences wouldremainwithintheirestablished acceptance criteriawhenincluding theeffectsofincreased RCSflow,increased lowflowtripsetpoint, andchangetothethyroiddoseconversion factorsusedinthedetermination of

St.LucioUnit1DocketNo.50-335ProposedLicenseAmendment CS'uowandSUdateL-98-283Attachment 2Page2of2doseconsequences.

ProposedchangestotheBasesfortheSteamGenerator Pressure-Low tripsetpoint, fuelstoragedesignfeatures, andthelistofanalytical methodsinTS6.9.1.11areadministrative innatureanddonotimpactcurrentsafetyanalyses.

Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

(2)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Thisproposedamendment reviseslimitingflowparameters toderiveanalysisbenefitsfromincreased RCSflowduetothereplacement steamgenerators, whileassuringsafeplantoperation commensurate withtheproposedRCSflowandlowflowtripsetpointchanges.ThesechangesalongwiththeproposedchangestotheBasesfortheSteamGenerator Pressure-Low tripsetpoint, doseconversion factors,thelistofanalytical methodsinTS6.9.1.11, andthefuelstoragedesignfeaturesdonotrequiremodifications totheplantconfiguration, systemsorcomponents whichwouldcreatenewfailuremodes.,Therewouldbenochangeinthemodesofoperation oftheplant.Thedesignfunctions ofallthesafetysystemsremainunchanged.

Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

(3)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Theproposedamendment reviseslimitingflowparameters toderiveanalysisbenefitsfromincreased RCSflowduetothereplacement steamgenerators, whileassuringsafeplantoperation commensurate withtheproposeddesignminimumRCSflowandlow-flowtripsetpointchanges.FPLhasevaluated theimpactoftheproposedchangesonavailable margintotheacceptance criteriaforSpecified Acceptable FuelDesignLimits(SAFDL),10CFR50.46(b) requirements, primaryandsecondary over-pressurization, peakcontainment

pressure, potential radioactive

releases, andexistinglimitingconditions foroperation.

WiththeproposedchangestothedesignminimumRCSflow,low-flowtripsetpoint, anddoseconversion factors,FPLhasconcluded thattherewouldbenoadverseimpacttotheexistingsafetyanalyses.

TheproposedchangestotheBasesfortheSteamGenerator Pressure-Lowtripsetpoint, thelistofanalytical methodsinTS6.9.1.11, andthefuelstoragedesignfeaturesareadministrative innature.Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Basedonthediscussion presented aboveandonthesupporting Evaluation ofProposedTSChanges,FPLhasconcluded thatthisproposedlicenseamendment involvesnosignificant hazardsconsideration.