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{{#Wiki_filter:00Q)~s)UN>lVjno'w,'QINO~,'OOMOQIQau+ | {{#Wiki_filter:00Q)~s)UN>lVjno'w,'QINO~,'OOMOQIQau+FUNCTIONAL UNIT1.ManualReactorTrip2.PowerLevel-High(1)TABLE2.2-1TRIPSETPOINTNotApplicable ALLOWABLE VALUESNotApplicable REACTORPROTECTIVE INSTRUMENTATION TRIPSETPOINT-LIMITSFourReactorCoolantPumpsOperating 3.ReactorCoolantFlow-Low(1)FourReactorCoolantPumpsOperating 4.Pressurizer Pressure-High5.Containment Pressure-High6.SteamGenerator Pressure-Low(2)7.SteamGenerator WaterLevel-Low8.LocalPowerDensity-High(3)<9.61$aboveTHERMALPOWER,withaminimumsetpointof15$ofRATEDTHERMALPOWER,andamaximumof<107.0g,ofRATEDTHERMALPOWER.>95'fdesignreactorcoolant7lowwith4pumpsoperating* | ||
<2400psia<3.3psig>600psia>37.0$,WaterLevel-eachsteamgenerator TripsetpointadjustedtonotexceedthelimitlinesofFigures2.2-1and2.2-2<9.61'XaboveTHERMALPOWER,andaminimumsetpointof15$ofRATEDTHERMALPOWERandamaximumof<107.0$ofRATEOTHERMALPOWER.>951,ofdesignreactorcoolantf'lowwith4pumpsoperating* | |||
<2400psia<3.3psig>600ps>a>37.0$WaterLevel-eachsteamgenerator TripsetpointadjustedtonotexceedthelimitlinesofFigures2.2-1and2.2-2.*Designreactorcoolantflowwith4pumpsoperating is370,000gpm.IPOGOI00 | |||
)~~ | )~~ | ||
TABLE3.3- | TABLE3.3-4ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION TRIPVALUESFUNCTIONAL UNIT1.SAFETYINJECTION (SIAS)a.Manual(TripButtons)b.Containment Pressure-Highc.Pressurizer Pressure-Low2.CONTAINMENT SPRAY(CSAS)a.Manual(TripButtons)b.Containment Pressure--High-High TRIPSETPOINTNotApplicable | ||
TABLE3.3- | <5psig>1600psiaNotApplicable | ||
''TABLE'7;3.2- | <10psigALLOWABLE VALUESNotApplicable 5psig>1600psiaNotApplicable<10psig3.CONTAINMEHTISOLATION (CIS)a.Manual(TripButtons)b.Containment Pressure-Highc.Containment Radiation | ||
''TABL'E7.3;2- | -Highd.SIASHotApplicable HotApplicable | ||
+10002LOOP- | <5psig<5psig<10R/hr<10R/hr(SEEFUNCTIONAL UNIT1ABOVE)-4.MAINSTEAMLINEISOLATION (MSIS)a.Manual(TripButtons)b.SteamGenerator Pressure-LowHotApplicable | ||
~II>~5002LOOP-NOLOAD000C3Vl'500C)w.200.~:AFFECTEDSTEAN6EHERATOR~~ | >585psigNotApplicable | ||
~f~(cl100902LOOP-NOlOAD8070>-"604030.2010p~001200300.400.TIME,SECONDS500.6COFLOa[OAPOV<'ERcLIGHTCO.St.LuciaPlantUnitlSTEAhlLTiilER~JPTUREEVEiMTFEEDS/ | >585psig5.CONTAINMENT SUMPRECIRCULATION (RAS)a.'anualRAS(TripButtons)b.Refueling WaterTank-LowNotApplicable NotApplicable 48inchesabovetankbottom48inchesabovetankbottom 2.2LIMITINGSAFETYSYSTEMSETTINGSBASESREACTORCOOLANTFLOW-LOWContinued reactorcoolantpumpsaretakenoutofservice.Thelow-flowtripsetpoints andAllowable Valuesforthevariousreactorcoolantpumpcombinations havebeenderivedinconsideration ofinstrument errorsandresponsetimesofequipment involvedtomaintaintheDNBRabove1.30undernormaloperation andexpectedtransients. | ||
,1201002LOOP-HOLOADI9080X706040-3020~o10001002003CO400TIME,SECONDSFLORtDAPAYER8,l.lGHTCO,S<.LvcicPlantilail)SEAMLIibERUPURE'VEJ')T-COREAiJFRAG' | Forreactoroperation withonlytwoorthreereactorcoolantpumpsoperating, theReactorCoolantFlow-Lowtripsetpoints, thePowerLevel-High tripsetpoints, andtheThermalMargin/Low Presuretripsetpoints areautomatically changedwhenthepumpcondition selectorswitchismanuallysettothedesiredtwo-orthree-pump position. | ||
Changingthesetripsetpoints duringtwoandthreepumpoperation preventstheminimumvalueofDNBRfromgoingbelow1.30duringnormaloperational transients andanticipated transients whenonlytwoorthreereactorcoolantpumpsareoperating. | |||
Pressurizer Pressure-Hi hThePressurizer Pressure-High trip,backedupbythepressurizer codesafetyvalvesandmainsteamlinesafetyvalves,provides.reactorcoolantsystemprotection againstoverpressurization intheeventoflossofloadwithoutreactortrip.Th'.strip'ssetpo'.nt is100psibelowthenominalliftsetting(2500psia)ofthepressurizer codesafetyvalvesanditsconcurrent operation withthepower-operated reliefvalvesavoidstheundesirable operation ofthepressurizer codesafetyvalves.Containment Pressure-High TheContainment Pressure-High tripprovidesassurance thatareactortripisinitiated concurrently withasafetyinjection. | |||
SteamGenerator Pressure-Low TheSteamGenerator Pressure-Low tripprovidesprotection againstanexcessive rateofheatextraction fromthesteamgenerators andsubsequent cooldownofthereactorcoolant.'Thesettingof600psiaissufficiently belowthefull-load operating pointof800psigsoasnotST.LUCIE-Unit1B2-57-23-81 TABLE2.2-1Continued REACTORPROTECTIVE INSTRUMENTATION TRIPSETPOINTLIMITSFUNCTIONAL UNIT9.ThermalMargin/Low Pressure(1)FourReactorCoolantPumpsOperating 10.LossofTurbine-Hydraulic FluidPressure-Low(3)ll.RateofChangeofPower-High(4)TRIPSETPOINTTripsetpointadjustedtonotexceedthelimitlinesofFigures2.2-3and2.2-4.>800psig<2.49decadesperminuteALLOWABLE VALUESTripsetpointadjustedtonotexceedthelimitlinesofFigures2.2-3and2.2-4.>800psig<2.49decadesperminuteTABLENOTATION(1)Tripmaybebypassedbelow1$ofRATEDTHERMALPOWER;bypassshallbeautomatically removedwhenTHERMALPOWERis>lgofRATEDTHERMALPOWER(2)Tripmaybemanuallybypassedbelow685psig;bypassshallbeautomtically removedatorabove685psig.(3)Tripmaybebypassedbelow15$ofRATEDTHERMALPOWER;bypassshallbeautomatically removedwhenTHERMALPOWERis>15$ofRATEDTHERMALPOWER.(4)Tripmaybebypassedbelow105andabove15$ofRATL'DTHERMALPOWER. | |||
TABLE3.3-3Continued TABLENOTATION(a)TripfunctionmaybebypassedinthisMODEwhenpressurizer pressureis<1725psia;bypassshallbeautomtically removedwhenpressurizer pressureis>1725psia.(b)AnSIASsignalisfirstnecessary toenableCSASlogic.(c)TripfunctionmaybebypassedinthisMODEbelow685psig;bypassshallbeautomatically removedatorabove685psig.Theprovisions ofSpecification 3.0.4arenotapplicable. | |||
ACTIONSTATEMENTS ACTION8ACTION9WiththenumberofOPERABLEchannelsonelessthantheTotalNumberofChannels, restoretheinoperable channeltoOPERABLEstatuswithin48hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WiththenumberofOPERABLEchannelsonelessthantheTotalNumberofChannels, operation mayproceedprovidedthefollowing conditions aresatisified: | |||
a.Theinoperable channelisplacedineitherthebypassedortrippedcondition within1hour.Forthepurposesoftestingandmaintenance, theinoperable channelmaybebypassedforupto48hoursfromtimeofintiallossofOPERABILITY; however,theinoperable channelshallthenbeeitherrestoredtoOPERABLEstatusorplacedinthetripped,condition. | |||
b.Withinonehour,allfunctional unitsreceiving aninputfromtheinoperable channelarealsoplacedinthesamecondition (eitherbypassedortripped,asapplicable) asthatrequiredbya.abovefortheinoperable channel.c.TheMinimumChannelsOPERABLErequirement ismet;however,oneadditonal channelmaybebypassedforupto48hourswhileperforming testsandmaintenance onthatchannelprovidedtheotherinoperable channelisplacedinthetrippedcondition. | |||
STLUCIE-UNIT13/43-127-23-81 0TABLE3.2.-1Continued TABLENOTATION*Withtheprotective systemtripbreakersintheclosedpositionandtheCEAdrivesystemcapableofCEAwithdrawal. | |||
gTheprovisions ofSpecification 3.0.4arenotapplicable. | |||
(a)Tripmaybebypassedbelow1$,ofRATEDTHERMALPOWER;bypassshallbeautomatically removedwhenTHERMALPOWERis>lg,.ofRATEDTHERMALPOWER.(b)Tripmaybemanuallybypassedbelow685psig;bypassshallbeautomatically removedatorabove685psig.(c)Tripmaybebypassedbelow155ofRATEDTHERMALPOWER;bypassshallbeautomatically removedwhenTHERMALPOWERis>15$ofRATEDTHERMALPOWER.(d)Tripmaybebypassedbelow105andabove15$ofRATEDTHERMALPOWER;bypassshallbeautomtically removedwhenTHERMALPOWERis>10"5or<15$ofRATEDTHERMALPOWER.(e)TripmaybebypassedduringtestingpursuanttoSpecialTestException 3.10.3.(f)ThereshallbeatleasttwodecadesofoverlapbetweentheWideRangeLogarithmic NeutronFluxMonitoring ChannelsandthePowerRangeNeutronFluxMonitoring Channels. | |||
ACTIONSTATEMENTS ACTION1ACTION2WithnumberofchannelsOPERABLEonelessthanrequiredbytheMinimumChannelsOPERABLErequirement,restoretheinoperable channeltoOPERABLEstatuswithin48hoursorbeinHOTSTANDBYwithinthenext6hoursand/oropentheprotective systemtripbreakers. | |||
WiththenumberofOPERABLEchannelsonelessthantheTotalNumberofChannels, STARTUPand/orPOWEROPERATION maypoceedprovidedthefollowing conditions aresatisfied: | |||
a.Theinoperable channelisplacedineitherthebypassedortrippedcondition within1hour.Forthepurposesoftestingandmaintenance, theinoperable channelmaybebypassedforupto48hoursfromtimeofinitiallossofOPERABILITY; however,theinoperable channelshal1thenbeeitherrestoredtoOPERABLEstatusorplacedinthetrippedcondition. | |||
ST.LUCIE-UNIT13/43-47-23-81 03/4.1REACTIVITY CONTROLSYSTEMSBASES3/4.1.1BORATIONCONTROL3/4.1.1.1 AND3/4.1.1.2 SHUTDOWNMARGINAsufficient SHUTDOWNMARGINensuresthat1)thereactorcanbemadesubcriticalfromalloperating conditions, 2)thereactivity transientsassociatedwithpostulatedaccidentconditionsarecontrollablewithinacceptable limits,and3)thereactorwillbemaintained sufficiently subcritical toprecludeinadvertent criticality intheshutdowncondition. | |||
SHUTDOWNMARGINrequirements varythroughout corelifeasafunctionoffueldepletion, RCSboronconcentration, andRCSTav~Themostrestrictive condition occursatEOL,withTavatnoloadoperating temperature, andisassociatedwithapostulatedsteamlinebreakaccidentandresultinguncontrol 1edRCScooldown.Intheanalysisofthisaccident, aminimumSHUTDOWNMARGINof5.Og,d.k/kisrequiredtocontrolthereactivityItransient. | |||
Accordingly, theSHUTDOWNMARGINrequiredbySpecification 3.1.1.1isbaseduponthislimitingcondition andisconsistent withFSARaccidentanalysisassumptions. | |||
Forearlierperiodsduringthefuelcycle,this'valueisconservative. | |||
WithTav<200'F,thereactivity transients resulting fromanypostulated accidentaPeminimalanda1$dk/kshutdownmarginprovidesadequateprotection. | |||
3/4.1.1.3 BORONDILUTIONANDADDITIONAminimumflowrateofatleast3000GPMprovidesadequatemixing,preventsstratification andensuresthatreactivity changeswillbegradualduringboronconcentration changesintheReactorCoolantSystem.Aflowrateofatleast3000GPMwillcirculate anequivalent ReactorCoolantSystemvolumeof'11,400cubicfeetinapproximately 26minutes.Thereactivitychangerateassoicated withboronconcentration changeswillbewithinthecapability foroperatorrecognition andcontrol.3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT MTCThelimitingvaluesassumedfortheMTCusedintheaccidentandtransient analyseswere+0.5x104hk/k/'FforTHERMALPOWERlevels<7%ofRATEDTHERMALPOWER,+0.2x104hk/k/'FforTHERMALPOWERlevels>70%,ofRATEDTHERMALand-2.2x104hk/k/'FatRATEDTHERMALPOWER.Therefore, theselimitingvaluesareincludedinthisspecification. | |||
Determination ofMTCatthespecified conditions ensuresthatthemaximumpositiveand/ornegativevaluesoftheMTCwillnotexceedthelimitingvalues.ST.LUCIE-UNIT1B3/41-17-23-81 3/4.1REACTIVITY CONTROLSYSTEMS3/4.1.1BORATIONCONTROLSHUTDOWNMARGINTav>200FLIMITINGCONDITION FOROPERATION 3.1.1.1TheSHUTDOWNMARGINshal1be>5.0$bk/k.APPLICABILITY: | |||
MODES1,2*,3and4.ACTION:WiththeSHUTDOWNMARGIN<5.l@dk/k,immediately initiateandcontinueborationat>40gpmof1720ppmboronorequivalent untiltherequiredSHUTDOWNMARGTNisrestored. | |||
SURVEILLANCE REUIREMENTS 4.1.1.1.1 TheSHUTDOWNMARGINshallbedetermined tobe>5.0$~k/k:a.Withinonehourafterdetection ofaninoperable CEA(s)andatleastonceper12hoursthereafter whiletheCEA(s)isinoperable. | |||
Iftheinoperable CEAisimmovable oruntrippable, theaboverequiredSHUTDOWNMARGINshallbeincreased byanamountatleastequaltothewithdrawn worthoftheimmovable oruntrippable CEA(s).b.,WheninMODES1or2g,atleastonceper12hoursbyverifying thatCEAgroupwithdrawal iswithinthePowerDependent Insertion LimitsofSpecification 3.2.3.6.cd.WheninMODE2gg,atleastonceduringCEAwithdrawal andatleastonceperhourthereafter untilthereactoriscritical. | |||
Priortoinitialoperation above5$RATEDTHERMALPOWERaftereachfuelloading,byconsideration ofthefactorsofebelow,withtheCEAgroupsatthePowerDependent InsertionLimitsofSpecification3.1.3.6.SeeSpecialTestException 3.10.1.WithKeff>1.0WithKeff<1.0.STLUCIE-UNIT13/41-17-23-81 REACTIVITY CONTROLSYSTEMSSURVEILLANCE REUIREMENTS Continued e..WheninMODES3or4,atleastonceper24hoursbyconsideration ofthefollowing factors:1.Reactorcoolantsystemboronconcentration, 2.CEAposition"3.Reactorcoolantsystemaveragetemperature, 4.Fuelburnupbasedongrossthermalenergygeneration, 5.Xenonconcentration, and6.Samariumconcentration. | |||
4.1.1.1.2 Theoverallcorereactivity balanceshallbecomparedtopredicted valuestodemonstrate agreement within+1.0$<k/katleastonceper31Effective Full.PowerDays(EFPD).Thiscomparison shallconsideratleastthosefactorsstatedinSpecification 4.1.1.1.l.e, above.Thepredicted reactivity valuesshallbeadjusted(normalized) tocorrespond totheactualcoreconditions priortoexceeding afuelburnupof60Effective FullPowerDaysaftereachfuelloading.*ForModes3and4,duringcalcuation ofshutdownmarginwithallCEA'sverifiedfullyinserted, thesingleCEAwiththehighestreactivity worthneednotbeassumedtobestuckinthefullywithdrawn position. | |||
ST.LUCIE-UNIT13/41-27-23-81 3/4.4REACTORCOOLANTSYSTEMREACTORCOOLANTLOOPSLIMITINGCONDITION FOROPERATION 3.4.1Fourreactorcoolantpumpsshallbeinoperation. | |||
APPLICABILITY: | |||
Asnotedbelow,butexcluding MODE6.ACTION:MODES1and2:Withlessthanfourreactorcoolantpumpsinoperation, beipatleastHOTSTANDBYwithin6hours.MODES3,4and5:Operation mayproceedprovided(1)atleastonereactorcoolantloopisinoperation withanassociated reactorcoolantpumporshutdowncoolingpumpand(2)theSHUTOOMNMARGINrequirmnent ofSpecification 3.1.1.1isincreased toandmaintained at>5.0Sak/kduringoperation inNOOE3whenlessthanfourreactorcoolantpumpsareinoperation. | |||
Theprovisions ofSpecifications 3.0.3and3.0.4arenotapplicable. | |||
SURVEILLANCE REUIREMENT4.4.1TheFlowDependent SelectorSwitchshallbedetermined tobeinthe4pumppositionwithin15minutespriortomakingthereactorcriticalandatleastonceper12hoursthereafter Al1reactorcoolantpumpsandshutdowncoolingpumpsmaybede-energized forupto1hour,providednooperations arepermitted whichcouldcausedilutionofthereactorcoolantsystemboronconcentration. | |||
ST.LUCIE-UNIT13/44-17-23-81 DESIGNFEATURES5.2.1.2SHIELDBUILDINGa.Minimumannularspace=4feet.b.Annulusnominalvolume=543,000cubicfeet.c.Nominaloutsideheight(measured fromtopoffoundation basetothetopofthedome)=230.5feet.d.Nominalinsidediameter=148feet.e.Cylinderwallminimumthickness | |||
=3feet.f.Domeminimumthickness | |||
=2.5feet.g.Domeinsideradius=112feet.DESIGNPRESSUREANDTEMPERATURE 5.2.2Thecontainment vesselisdesignedandshal1bemaintained foramaximuminternalpressureof44psigandatemperature of264'F.PENETRATIONS 5.2.3Penetrations throughthecontainment structure aredesignedandshallbemaintained inaccordance withtheoriginaldesignprovisions contained inSections3.8.2.1.10and6.2.4oftheFSARwithallowance fornormaldegradation pursuanttotheapplicable Surveillance Requirements. | |||
5.3REACTORCOREFUELASSEMBLIES 5.3.1Thereactorcoreshallcontain217fuelassemblies witheachfuelassemblycontaining amaximumof176fuelrodscladwithZircoloy-4.Eachfuelrodshallhaveanaoinalactivefuellengthof136.7inchesandcontainamaximumtotalweightof2250gramsuranium.Theinitialcoreloadingshallhaveamaximumenrichment of2.83weightpercentU-235.Reloadfuelshallbesimilar-inphysicaldesigntotheinitialcoreloading.5.3.2Except,forspecialtestasauthorized bytheNRC,allfuelassemblies | |||
.ndercontrolelementassemblies shallbesleevedwithasleevedesignpreviously approvedbytheNRC.ST.LUCIE-UNIT15-47-23-81 Two-Loop-2754 MHtTheTwoLoop-2754 MWtcasewasinitiated attheconditions listedinTable7.3.2-1.TheModerator Temperature Coefficient (MTC)ofreactivity assumedin-theanalysiscorrespondstoendoflife,sincethisnegativeMTCresultsinthegreatestpositivereactivity additionduringtheRCScooldowncausedbytheSteamLineRupture.Sincethereactivity changeassociated withmoderator feedbackvariessignificantly overthemoderator densitycoveredintheanalysis, acurveofreactivity insertion versusdensityratherthanasinglevalueofMTCisassumedintheanalysis. | |||
Themoderator cooldowncurvegiveninFigure7.3.2-1wasconservatively calculated assumingthatonreactorscram,thehighestworthControlElementAssemblyisstuckinthefullywithdrawn position. | |||
Thereactivity defectassociated withfueltemperature decreaseisalsobasedonendoflifeDopplerdefect.TheDopplerdefectbasedonanendoflifeFuelTemperature Coefficient (FTC),inconjunction withthedecreasing fueltemperatures, causesthegreatestpositivereactivity insertion duringtheSteamLineRuptureevent.Theuncertainty ontheFTCassumedintheanalysisisgiveninTable7.3.2-1.The8fractionassumedisthemaximumabsolutevalueincluding uncertainties forendoflifeconditions. | |||
Thistooisconservative sinceitmaximizes subcritical multiplication andthus,enhancesthepotential forReturn-to-Power (R-T-P).TheminimumCEAworthassumedtobeavailable forshutdownatthetimeofreactortripatthemaximumallowedpowerlevelis6.74Xap.Thisavailable scramworthwascalculated forthestuckrodwhichproducedthemoderator cooldowncurveinFigure7.3.2-1.Theanalysisconservatively assumedthat,onSafetyInjection Actuation Signal,oneHiqhPressureSafetyInjection pumpfailstosta'rt.Theanalysisalsoassumedacons'ervatively lowvalueofboronreactivity worthof-1.0Ãhpper105PPM.Theconservative assumptions onfee'dwater flowwerediscussed previously. | |||
Thefeedwater flowandenthalpyasafunctionoftimearepresented inFigures7.3.2-2and7.3.2-3respectively. | |||
Table7.3.2-2presentsthesequenceofeventsforthefullpowercaseinitiated attheconditions giveninTable7.3.2-1.Thereactivity in-sertionasafunctionoftimeispresented inFigure7.3.2-4.TheresponseoftheNSSSduringthiseventisgiveninFigures<,3.2-5through7.3.2-9.TheresultsoftheanalysesshowthatSIASisactuatedat15seconds,atwhichtimetheReactorCoolantPumpsaremanuallytrippedbytheoperator. | |||
ThemanualtripofRCP'sslowsdowntherateofprimaryheatremovalandthusdelaysthetimewhentheaffectedsteamgenerator blowsdry.Theaffectedsteamgenerator blowsdryat154secondsandtermi-natesthecooldownoftheRCS.Thepeakreactivity attainedpriortodeliveryofauxiliary feedwater flowis-.205Ãapat169seconds.Apeakposttrippowerofl4.0~,consisting of12.2'Xdecayheatand1.8'Xfissionpower,isproducedat72.8seconds.. | |||
Thecontinued production ofdecayheatfromthefuelaftertermination ofblowdown, causesthereactorcoolanttemperatures toincrease. | |||
Thisinturnreducesthemagnitude ofthepositivemoderator reactivity insertedandthusthetotalreactivity becomesmorenegative. | |||
7-23-81 Thedeliveryofauxiliary feedwater flowtotheaffectedsteamgenerator at180secondsinitiates afurthercooldownoftheRCSwhichresultsinmorepositivereactivity insertion. | |||
However,continued additionofnegativereactivity bytheboroninjectedviatheHPSIpumppreventsthepositivereactivity insertion ofthemoderator fromcausingareturnto.criticality.'he coreremainssubcritical throughout | |||
'heremainder ofthetransient. | |||
TheSteamLineRuptureeventfromHFPconditions withautomatic initiation ofauxiliary feedwater andmanualtripofRCP'sonSIASshowsthatthecoredoesnotproducesignificant instantaneous fissionpower.Sincethereisnosignificant Return-to-Power, itcanbeconcluded thatcriticalheatfluxeswi-llnotheexceeded. | |||
TwoLoo-NoLoadThetwoLoop-NoLoadcasewasinitiated attheconditions qiveninTable7.3.2-3.Themoderator cooldowncurveisgiveninFiqure7.3.2-10. | |||
Thecooldowncurvecorresponds toanendoflifeNTC.AnendoflifeFTCwasalsousedforthereasonspreviously discussed inconnection withtheTwoLoop-2754 MWtcase.TheminimumCEAshutdownworthavailable isconservatively assumedtobetheminimumrequiredTechnical Specification limitof5.0hp.Amaximuminverseboronworthof80PPH/Rapwasconservatively assumedforthesafetyinjection duringthenoloadcase.Thefeedwater flowandtheenthalpyusedintheanalysisarepresented inFigures7.3.2-11and7.3.2-12.respectively. | |||
>IhenallCEA'sareverifiedtobefullyinserted(duringmodes3and4)iisnotnecessary toassureone(theoneofhighestreactivity worth)isstuckinafullywithdrawn positionwhencalculating shutdownmargin.Table7.3.2-4presentsthesequenceofeventsfortheTwoLoop-NoLoadcaseinitiated fromtheconditions giveninTable7.3.2-3.Thereactivity insertion asafunctionoftimeispresented inFigure7.3.2-13. | |||
Theresponse-ofkeyNSSSparameters during-thiseventaregiveninFigures7.3.2-'l4 | |||
'hrough7.3.2-18. | |||
TheresultsoftheanalysisshowthatSIASisactuatedat12.0seconds,atwhichtimetheRCP'saremanuallytrippedbytheoperator. | |||
Theaffectedsteamgenerator blowsdryat180.0seconds.Auxiliary feed-waterflowisinitiated at180.1secondswhichcontinues thecooldownoftheRCS.Thus,thetotalcorereactivity iscritical'for ashortperiodoftime.Thepeakreactivity attainedisonly+.140Kapat401.0seconds.TheadditionofboronviaHighPressureSafetyInjection mitiqates thereactivity transient. | |||
Thecorepowerlevelremainslessthan1%ofratedpoweratalltimesduringtheevent.Sincethereisnosignificant R-T-PfortheTwoLoop-NoLoadcase,itcanbeconcluded thatthecriticalheatfluxwillnotbeexceededduringthisevent. | |||
''TABLE'7;3.2-1 KEYPARAMETERS ASSUMEDINTHESTEAMLINERUPTUREANALYSIS2-LOOP-2754 MWTParameter InitialCorePowerInitialCoreInletTemperature InitialRCSPressureInitialCoreMassFlowRateInitialSteamGenerator PressureMinimumCEAWorthAvailable atTrip~..Doppler.Multiplier Moderator CooldownCurveInverseBoronWorthEffective FullPowerMTCgFraction(including, uncertainties)'ni tsoFpslax10ibm/hrps1aCapvs.densityPPM/Xnpx10ap/FReference CcIe*27545512300'33.8'909W.251.15SeeFigure7.3.2-1105-25.0060~Ccie527545512300133.8900-6.741.15SeeFigure7.3.2-1105<<2e2.0060*(Note:Thelastcompleteblowdown. | |||
analysisforthiseventwasperformed fortheCycle4stretchpowersubmittal.) | |||
''TABL'E7.3;2-2SEQUENCEOFEVENTSFORSTEAMLINERUPTUREEVENTWITHAUTOMATIC INITIATION OFAUXILIARY FEEDWATER ANDMANUALTRIPOFREACTORCOOLANTPUMP2-LOOP-2754 MWTTimesec)0.02.32.3.Qo23.2EventSteamLineRuptureOccursLowSteamGenerator PressureTripSignalOccursMainSteamIsolation Signalgenerated MainSteamIsolation ValvesBegintoClose,TripBreakersOpenSetointorValue578psia578psia3.7'9.214.615.015.045.063.372.8154.5'69.0 180.0600.0CEAsBegintoDropintoCoreMainSteamIsolation ValvesCompletely ClosedPressurizer Empties:SafetyInjection Actuation SignalReactorCoolantPumpsManuallyTrippedHighPressureSafetyInjection PumpsStartHainFeedwater Isolation PeakPost.TripPowerAffectedSteamGenerator BlowsDryPeakReactivity, PriortoAuxiliary Feedwater FlowAuxiliary Feedwater FlowInitiated toRupturedSteamGenerator OperatorIsolatesRupturedSteamGenerator andTerminates Auxiliary Feedwater Flow1578.0psia14.05-.205'ap253.6ibm/sec7-23-81 Isss'TABLE'7;3;2-3 KEYPARAMETERS ASSUMEDINTHESTEAMLINERUPTUREANALYSIS2-LOOP,NOLOADParameter InitialCorePowerInitialCoreInletTemperature InitialRCSPressureInitialSteamGenerator PressureMinimumCEAWorthAvailab1eatTripDopplerMultiplier Moderator CooldownCurveInverseBoron1<orthEffective FullPowerMTC.gFracti.on (including uncertainty) | |||
UnitsMWt'oFpsiapsiaCapvs.densityPPM/lap10ap/FReference | |||
~Ccle*1.05322300'00-4.31.15SeeFigure7.3.2-10100-28'0060~Cele51.05322300900-5.00;85SeeFigure7.3.2-10802%2.0060.*Cycle4stretchpowersubmittal 7-23-81 TABLE7;3.2-4SEQUENCEOFEVENTSFORSTEAMLiNERUPTUREEVENTWITHAUTOMATIC INITIATION OFAUXILIARY FEEDWATER ANDMANUALTRIPOFREACTORCOOLANTPUMPS2-LOOP,NOLOADTimesec0.03.8.3.84.74.75.210.210.712.0'2.042.086.0180.0180.1401.0520.0600.0EventSteamLineRuptureOccurs'ILowSteamGenerator PressureTripSignalOccursMainSteamIsolation, SignalGenerated MainSteamIsolation ValvesBegintoCloseTripBreakersOpenCEAsBegintoDropIntoCorePressurizer EmptiesMainSteamIsolation ValvesCompletely ClosedSafety.Injection Actuation SignalReactorCoolantPumpsManuallyTrippedHighPressureSafetyInjection PumpsStartHainFeedwater Isolation AffectedSteamGenerator BlowsDryAuxiliary Feedwater FlowInitiated toRupturedSteamGenerator PeakReactivity ReturntoPowerOperatorIsolatesRupturedSteamGenerator andTerminates Auxiliary Feedwater FlowSetointorValue578.0psia578.0psia1578.0psia253.6ibm/sec+e140Xapc15ofratedpower7-23-81 2LOOP-FULL PONERCYCLEIICYCLE50QO5055DENSITY;LBi'l/CUBIC FT60657-23-81FLORIDAPOWER8.LIGHTCo.St.LuciePfantSTEAMLINEBREAKEVENTMODERATOR REACTIVIT'( | |||
FEEDBACKvsunnco<Tnonet,c:TT'4 | |||
.7,3,2-1 180016002LOOP-FULL POHER1I40012001000800600000-200.0-2000100AFFECTEDSGUNAFFECTED SG'00'001100TINE,SECONDS500600'LORLDAPOWER8LIGHTCO.5t.LvciePlantUnit1STEAMLINE8REAKEVENTFEED>YATER FLOVlvsTIME713I2-27-23-81 5000002LOOPFULLPOWER300~.200100,00100200300<100TINE,SECONDS500600FLORIDAPOV/ER8LIGHTCO.St.LuciePlantUnit3.STEAMLINE8REAKEVENTFEEDV/ATER EHTHALPYvsTIME7,3,2--"7-23-81 2LOOP-FULL PONERrtODERATOR DOPPLER00-t-jUJBOROI'lTOTO.LISCRAMRODS010020000F00TINE,SECONDS500.6007-23-81FLORIDAPOKIER8LIGHTCO.St.LvciePlantSTEAhlLINE8REAKEVENTnt.4f774/TTvi<<TTMF713I2 1201102-LOOPFOLLPOWER10088P70U.60~50g0030~201000100200300000TIl1E,SECOI'JDS 500600"LOR[DAPOV/ER8LIGHTCO.St.LuciePlantUnit1STEAMLINEBREAKQUENTCOREPOVlERv~TIME7,3,2-57-23-81 01002LOCP-FULL PONERI-CDCDUCD8060C;eoUJ20'0100200=300TIi~iErSECONDS000500600FLORlDAPOWER8LlGHTCO.St.LuciePlantff'.a~STEAMLINEBREAKEVENTinot.-AifaoZt.~i-ivoryCt[IVi<<TTMP'-23-81 7,3,2-6 2LOOP-FULL POMER600O500I-900C=rco5~~20.0TP.VERAGE TINLETTOUTLET1000100200300000~TIME,SECONDS500600FLORIDA(POWER8LIGHTCO.9LuciePlantUnit17-23-81STEAMLINE8REAKEVENTREACTORCOOLANTSYSTEhTEMPERATURES vsTIME 29002LOOP-FULL POWER200016CO120088000200300900500600TINE,SECONDSFLORIDAPOWER8LIGHTCO.St.LuciePldnk7-23-81STEAh)LINEBREAKEVENTREACTORCOOLANT,SYSTEMPRESSUREvsTIl'hE732-8 | |||
+10002LOOP-FULL POWER+8COI-+600g+000+200UNAFFECTED SG0-.ZOO0100AFFECTEDSG200300L}00TIf'lE,SECONDS600FLORIDAPOWER8LIGHTgOSt.LuciePlantUnitlSTEAMLINE8REAKEVENTSTEAMGENERATOR PRESSURES vsTIME7-23-817,5,2-9 5.02LOOP-NOLOAD3.0~I-2.0CDl81.0CYCLE0CYCLE550.05S.Ot,'o.o65.0INODERATOR DENSITY,LBN/FT7-23-81FLORIDAPO%'ER8LIGHTCO.St.LuciePIontiS~~~STEAMLINERUPTUREQ(ENTMODERATOR R'ACTIVITY vsMOD"RATORDENSITYFigure7.3.2-10 | |||
~II>~5002LOOP-NOLOAD000C3Vl'500C)w.200.~:AFFECTEDSTEAN6EHERATOR | |||
~~F00UNAFFECTE DSTEAMGENERATOR | |||
.001002GO300400TIME,SECONDS500.600.FLORiDAPOVIER8LlGHTCO.St.LuciePlcntUnit1STEAMLINERUPTUREEVENTFEEDVlATER FLOVlvsTIME7-23-81Figvre7.3.2-11 | |||
~f~(cl100902LOOP-NOlOAD8070>-"604030.2010p~001200300.400.TIME,SECONDS500.6COFLOa[OAPOV<'ERcLIGHTCO.St.LuciaPlantUnitlSTEAhlLTiilER~JPTUREEVEiMTFEEDS/ATER ENTHALPYvsTIME7-23-81Figure7.3.2-~2 LOOP-NOLOADMODERATOR DOPPLER;TOTALBORONSCRAMRODV/ORTH100200300400TINE,SECQi~JDS 500600FLORIO'OVIER 8,LIGHTCO,St,LucicPion)UnitlSTEAMLIIXERUPTUR-EVENTREACTIVITY vsTIME7-23-81Figure7.3.2-1 0~l0~}00902LOOP-NOLQAD80.<7060CO.50,o403020.1000100200300400TXME;SECONDS500600FLORIOAPOPOVER8LIGHTCO.St.LuciaPlantUnit1STEAMLIt<ERUPTUREEVENTCOREPOVJERvsTItHE7-23-81Figure7.3.2-1 | |||
,1201002LOOP-HOLOADI9080X706040-3020~o10001002003CO400TIME,SECONDSFLORtDAPAYER8,l.lGHTCO,S<.LvcicPlantilail)SEAMLIibERUPURE'VEJ')T-COREAiJFRAG'EAT FLUXvsTIME7-23-81Figure7.3.2-15'; | |||
25002LOOP-f'LOLOAD2000a-1500~~>cooI500CD~~0~100200300400.TIME,SECONDS5006007-23-81FLORtDAPOViER8LlGHTCO,St,LucicPlantUnit1STEAMLINERL'PTVREEVENTREACTORCOOLANTSYSIcl'~'lPRESSUREvsTIMEFigyre7.3.2-1( | 25002LOOP-f'LOLOAD2000a-1500~~>cooI500CD~~0~100200300400.TIME,SECONDS5006007-23-81FLORtDAPOViER8LlGHTCO,St,LucicPlantUnit1STEAMLINERL'PTVREEVENTREACTORCOOLANTSYSIcl'~'lPRESSUREvsTIMEFigyre7.3.2-1( | ||
6002IOOP-NOLOAOc500~~400300~zooC)~100~ON~TOUTTAVE'~~~~i~e~~~~~+00100200300400TINE,SECONDS5006007-23-81FLO<locPO"/ER8,LlGHTCO,St,LuciePlantSTEAM.LIMERUPTUREEVENTREACTORCOOLANTSYSit: | 6002IOOP-NOLOAOc500~~400300~zooC)~100~ON~TOUTTAVE'~~~~i~e~~~~~+00100200300400TINE,SECONDS5006007-23-81FLO<locPO"/ER8,LlGHTCO,St,LuciePlantSTEAM.LIMERUPTUREEVENTREACTORCOOLANTSYSit:MTEMPERATURES vsTi.'AEFigre7.3.2-} | ||
10002.LOOP-NOLOAD800600400~>. | 10002.LOOP-NOLOAD800600400~>.200IUNAFFECTED SCAFFECTEDS6.-1000200300460TIME,SECONDSFLOR)DAPOV/ER6LfGHTCO.St.LuciaPlantUnitlSTEAMLINERUPTUREEVEiNTSTEAMGEi~,'ERATOR PRESSURES vsTIME7-23-81 | ||
~4}} | ~4}} | ||
Revision as of 17:55, 29 June 2018
| ML17212A423 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 07/23/1981 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17212A422 | List: |
| References | |
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Text
00Q)~s)UN>lVjno'w,'QINO~,'OOMOQIQau+FUNCTIONAL UNIT1.ManualReactorTrip2.PowerLevel-High(1)TABLE2.2-1TRIPSETPOINTNotApplicable ALLOWABLE VALUESNotApplicable REACTORPROTECTIVE INSTRUMENTATION TRIPSETPOINT-LIMITSFourReactorCoolantPumpsOperating 3.ReactorCoolantFlow-Low(1)FourReactorCoolantPumpsOperating 4.Pressurizer Pressure-High5.Containment Pressure-High6.SteamGenerator Pressure-Low(2)7.SteamGenerator WaterLevel-Low8.LocalPowerDensity-High(3)<9.61$aboveTHERMALPOWER,withaminimumsetpointof15$ofRATEDTHERMALPOWER,andamaximumof<107.0g,ofRATEDTHERMALPOWER.>95'fdesignreactorcoolant7lowwith4pumpsoperating*
<2400psia<3.3psig>600psia>37.0$,WaterLevel-eachsteamgenerator TripsetpointadjustedtonotexceedthelimitlinesofFigures2.2-1and2.2-2<9.61'XaboveTHERMALPOWER,andaminimumsetpointof15$ofRATEDTHERMALPOWERandamaximumof<107.0$ofRATEOTHERMALPOWER.>951,ofdesignreactorcoolantf'lowwith4pumpsoperating*
<2400psia<3.3psig>600ps>a>37.0$WaterLevel-eachsteamgenerator TripsetpointadjustedtonotexceedthelimitlinesofFigures2.2-1and2.2-2.*Designreactorcoolantflowwith4pumpsoperating is370,000gpm.IPOGOI00
)~~
TABLE3.3-4ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION TRIPVALUESFUNCTIONAL UNIT1.SAFETYINJECTION (SIAS)a.Manual(TripButtons)b.Containment Pressure-Highc.Pressurizer Pressure-Low2.CONTAINMENT SPRAY(CSAS)a.Manual(TripButtons)b.Containment Pressure--High-High TRIPSETPOINTNotApplicable
<5psig>1600psiaNotApplicable
<10psigALLOWABLE VALUESNotApplicable 5psig>1600psiaNotApplicable<10psig3.CONTAINMEHTISOLATION (CIS)a.Manual(TripButtons)b.Containment Pressure-Highc.Containment Radiation
-Highd.SIASHotApplicable HotApplicable
<5psig<5psig<10R/hr<10R/hr(SEEFUNCTIONAL UNIT1ABOVE)-4.MAINSTEAMLINEISOLATION (MSIS)a.Manual(TripButtons)b.SteamGenerator Pressure-LowHotApplicable
>585psigNotApplicable
>585psig5.CONTAINMENT SUMPRECIRCULATION (RAS)a.'anualRAS(TripButtons)b.Refueling WaterTank-LowNotApplicable NotApplicable 48inchesabovetankbottom48inchesabovetankbottom 2.2LIMITINGSAFETYSYSTEMSETTINGSBASESREACTORCOOLANTFLOW-LOWContinued reactorcoolantpumpsaretakenoutofservice.Thelow-flowtripsetpoints andAllowable Valuesforthevariousreactorcoolantpumpcombinations havebeenderivedinconsideration ofinstrument errorsandresponsetimesofequipment involvedtomaintaintheDNBRabove1.30undernormaloperation andexpectedtransients.
Forreactoroperation withonlytwoorthreereactorcoolantpumpsoperating, theReactorCoolantFlow-Lowtripsetpoints, thePowerLevel-High tripsetpoints, andtheThermalMargin/Low Presuretripsetpoints areautomatically changedwhenthepumpcondition selectorswitchismanuallysettothedesiredtwo-orthree-pump position.
Changingthesetripsetpoints duringtwoandthreepumpoperation preventstheminimumvalueofDNBRfromgoingbelow1.30duringnormaloperational transients andanticipated transients whenonlytwoorthreereactorcoolantpumpsareoperating.
Pressurizer Pressure-Hi hThePressurizer Pressure-High trip,backedupbythepressurizer codesafetyvalvesandmainsteamlinesafetyvalves,provides.reactorcoolantsystemprotection againstoverpressurization intheeventoflossofloadwithoutreactortrip.Th'.strip'ssetpo'.nt is100psibelowthenominalliftsetting(2500psia)ofthepressurizer codesafetyvalvesanditsconcurrent operation withthepower-operated reliefvalvesavoidstheundesirable operation ofthepressurizer codesafetyvalves.Containment Pressure-High TheContainment Pressure-High tripprovidesassurance thatareactortripisinitiated concurrently withasafetyinjection.
SteamGenerator Pressure-Low TheSteamGenerator Pressure-Low tripprovidesprotection againstanexcessive rateofheatextraction fromthesteamgenerators andsubsequent cooldownofthereactorcoolant.'Thesettingof600psiaissufficiently belowthefull-load operating pointof800psigsoasnotST.LUCIE-Unit1B2-57-23-81 TABLE2.2-1Continued REACTORPROTECTIVE INSTRUMENTATION TRIPSETPOINTLIMITSFUNCTIONAL UNIT9.ThermalMargin/Low Pressure(1)FourReactorCoolantPumpsOperating 10.LossofTurbine-Hydraulic FluidPressure-Low(3)ll.RateofChangeofPower-High(4)TRIPSETPOINTTripsetpointadjustedtonotexceedthelimitlinesofFigures2.2-3and2.2-4.>800psig<2.49decadesperminuteALLOWABLE VALUESTripsetpointadjustedtonotexceedthelimitlinesofFigures2.2-3and2.2-4.>800psig<2.49decadesperminuteTABLENOTATION(1)Tripmaybebypassedbelow1$ofRATEDTHERMALPOWER;bypassshallbeautomatically removedwhenTHERMALPOWERis>lgofRATEDTHERMALPOWER(2)Tripmaybemanuallybypassedbelow685psig;bypassshallbeautomtically removedatorabove685psig.(3)Tripmaybebypassedbelow15$ofRATEDTHERMALPOWER;bypassshallbeautomatically removedwhenTHERMALPOWERis>15$ofRATEDTHERMALPOWER.(4)Tripmaybebypassedbelow105andabove15$ofRATL'DTHERMALPOWER.
TABLE3.3-3Continued TABLENOTATION(a)TripfunctionmaybebypassedinthisMODEwhenpressurizer pressureis<1725psia;bypassshallbeautomtically removedwhenpressurizer pressureis>1725psia.(b)AnSIASsignalisfirstnecessary toenableCSASlogic.(c)TripfunctionmaybebypassedinthisMODEbelow685psig;bypassshallbeautomatically removedatorabove685psig.Theprovisions ofSpecification 3.0.4arenotapplicable.
ACTIONSTATEMENTS ACTION8ACTION9WiththenumberofOPERABLEchannelsonelessthantheTotalNumberofChannels, restoretheinoperable channeltoOPERABLEstatuswithin48hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WiththenumberofOPERABLEchannelsonelessthantheTotalNumberofChannels, operation mayproceedprovidedthefollowing conditions aresatisified:
a.Theinoperable channelisplacedineitherthebypassedortrippedcondition within1hour.Forthepurposesoftestingandmaintenance, theinoperable channelmaybebypassedforupto48hoursfromtimeofintiallossofOPERABILITY; however,theinoperable channelshallthenbeeitherrestoredtoOPERABLEstatusorplacedinthetripped,condition.
b.Withinonehour,allfunctional unitsreceiving aninputfromtheinoperable channelarealsoplacedinthesamecondition (eitherbypassedortripped,asapplicable) asthatrequiredbya.abovefortheinoperable channel.c.TheMinimumChannelsOPERABLErequirement ismet;however,oneadditonal channelmaybebypassedforupto48hourswhileperforming testsandmaintenance onthatchannelprovidedtheotherinoperable channelisplacedinthetrippedcondition.
STLUCIE-UNIT13/43-127-23-81 0TABLE3.2.-1Continued TABLENOTATION*Withtheprotective systemtripbreakersintheclosedpositionandtheCEAdrivesystemcapableofCEAwithdrawal.
gTheprovisions ofSpecification 3.0.4arenotapplicable.
(a)Tripmaybebypassedbelow1$,ofRATEDTHERMALPOWER;bypassshallbeautomatically removedwhenTHERMALPOWERis>lg,.ofRATEDTHERMALPOWER.(b)Tripmaybemanuallybypassedbelow685psig;bypassshallbeautomatically removedatorabove685psig.(c)Tripmaybebypassedbelow155ofRATEDTHERMALPOWER;bypassshallbeautomatically removedwhenTHERMALPOWERis>15$ofRATEDTHERMALPOWER.(d)Tripmaybebypassedbelow105andabove15$ofRATEDTHERMALPOWER;bypassshallbeautomtically removedwhenTHERMALPOWERis>10"5or<15$ofRATEDTHERMALPOWER.(e)TripmaybebypassedduringtestingpursuanttoSpecialTestException 3.10.3.(f)ThereshallbeatleasttwodecadesofoverlapbetweentheWideRangeLogarithmic NeutronFluxMonitoring ChannelsandthePowerRangeNeutronFluxMonitoring Channels.
ACTIONSTATEMENTS ACTION1ACTION2WithnumberofchannelsOPERABLEonelessthanrequiredbytheMinimumChannelsOPERABLErequirement,restoretheinoperable channeltoOPERABLEstatuswithin48hoursorbeinHOTSTANDBYwithinthenext6hoursand/oropentheprotective systemtripbreakers.
WiththenumberofOPERABLEchannelsonelessthantheTotalNumberofChannels, STARTUPand/orPOWEROPERATION maypoceedprovidedthefollowing conditions aresatisfied:
a.Theinoperable channelisplacedineitherthebypassedortrippedcondition within1hour.Forthepurposesoftestingandmaintenance, theinoperable channelmaybebypassedforupto48hoursfromtimeofinitiallossofOPERABILITY; however,theinoperable channelshal1thenbeeitherrestoredtoOPERABLEstatusorplacedinthetrippedcondition.
ST.LUCIE-UNIT13/43-47-23-81 03/4.1REACTIVITY CONTROLSYSTEMSBASES3/4.1.1BORATIONCONTROL3/4.1.1.1 AND3/4.1.1.2 SHUTDOWNMARGINAsufficient SHUTDOWNMARGINensuresthat1)thereactorcanbemadesubcriticalfromalloperating conditions, 2)thereactivity transientsassociatedwithpostulatedaccidentconditionsarecontrollablewithinacceptable limits,and3)thereactorwillbemaintained sufficiently subcritical toprecludeinadvertent criticality intheshutdowncondition.
SHUTDOWNMARGINrequirements varythroughout corelifeasafunctionoffueldepletion, RCSboronconcentration, andRCSTav~Themostrestrictive condition occursatEOL,withTavatnoloadoperating temperature, andisassociatedwithapostulatedsteamlinebreakaccidentandresultinguncontrol 1edRCScooldown.Intheanalysisofthisaccident, aminimumSHUTDOWNMARGINof5.Og,d.k/kisrequiredtocontrolthereactivityItransient.
Accordingly, theSHUTDOWNMARGINrequiredbySpecification 3.1.1.1isbaseduponthislimitingcondition andisconsistent withFSARaccidentanalysisassumptions.
Forearlierperiodsduringthefuelcycle,this'valueisconservative.
WithTav<200'F,thereactivity transients resulting fromanypostulated accidentaPeminimalanda1$dk/kshutdownmarginprovidesadequateprotection.
3/4.1.1.3 BORONDILUTIONANDADDITIONAminimumflowrateofatleast3000GPMprovidesadequatemixing,preventsstratification andensuresthatreactivity changeswillbegradualduringboronconcentration changesintheReactorCoolantSystem.Aflowrateofatleast3000GPMwillcirculate anequivalent ReactorCoolantSystemvolumeof'11,400cubicfeetinapproximately 26minutes.Thereactivitychangerateassoicated withboronconcentration changeswillbewithinthecapability foroperatorrecognition andcontrol.3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT MTCThelimitingvaluesassumedfortheMTCusedintheaccidentandtransient analyseswere+0.5x104hk/k/'FforTHERMALPOWERlevels<7%ofRATEDTHERMALPOWER,+0.2x104hk/k/'FforTHERMALPOWERlevels>70%,ofRATEDTHERMALand-2.2x104hk/k/'FatRATEDTHERMALPOWER.Therefore, theselimitingvaluesareincludedinthisspecification.
Determination ofMTCatthespecified conditions ensuresthatthemaximumpositiveand/ornegativevaluesoftheMTCwillnotexceedthelimitingvalues.ST.LUCIE-UNIT1B3/41-17-23-81 3/4.1REACTIVITY CONTROLSYSTEMS3/4.1.1BORATIONCONTROLSHUTDOWNMARGINTav>200FLIMITINGCONDITION FOROPERATION 3.1.1.1TheSHUTDOWNMARGINshal1be>5.0$bk/k.APPLICABILITY:
MODES1,2*,3and4.ACTION:WiththeSHUTDOWNMARGIN<5.l@dk/k,immediately initiateandcontinueborationat>40gpmof1720ppmboronorequivalent untiltherequiredSHUTDOWNMARGTNisrestored.
SURVEILLANCE REUIREMENTS 4.1.1.1.1 TheSHUTDOWNMARGINshallbedetermined tobe>5.0$~k/k:a.Withinonehourafterdetection ofaninoperable CEA(s)andatleastonceper12hoursthereafter whiletheCEA(s)isinoperable.
Iftheinoperable CEAisimmovable oruntrippable, theaboverequiredSHUTDOWNMARGINshallbeincreased byanamountatleastequaltothewithdrawn worthoftheimmovable oruntrippable CEA(s).b.,WheninMODES1or2g,atleastonceper12hoursbyverifying thatCEAgroupwithdrawal iswithinthePowerDependent Insertion LimitsofSpecification 3.2.3.6.cd.WheninMODE2gg,atleastonceduringCEAwithdrawal andatleastonceperhourthereafter untilthereactoriscritical.
Priortoinitialoperation above5$RATEDTHERMALPOWERaftereachfuelloading,byconsideration ofthefactorsofebelow,withtheCEAgroupsatthePowerDependent InsertionLimitsofSpecification3.1.3.6.SeeSpecialTestException 3.10.1.WithKeff>1.0WithKeff<1.0.STLUCIE-UNIT13/41-17-23-81 REACTIVITY CONTROLSYSTEMSSURVEILLANCE REUIREMENTS Continued e..WheninMODES3or4,atleastonceper24hoursbyconsideration ofthefollowing factors:1.Reactorcoolantsystemboronconcentration, 2.CEAposition"3.Reactorcoolantsystemaveragetemperature, 4.Fuelburnupbasedongrossthermalenergygeneration, 5.Xenonconcentration, and6.Samariumconcentration.
4.1.1.1.2 Theoverallcorereactivity balanceshallbecomparedtopredicted valuestodemonstrate agreement within+1.0$<k/katleastonceper31Effective Full.PowerDays(EFPD).Thiscomparison shallconsideratleastthosefactorsstatedinSpecification 4.1.1.1.l.e, above.Thepredicted reactivity valuesshallbeadjusted(normalized) tocorrespond totheactualcoreconditions priortoexceeding afuelburnupof60Effective FullPowerDaysaftereachfuelloading.*ForModes3and4,duringcalcuation ofshutdownmarginwithallCEA'sverifiedfullyinserted, thesingleCEAwiththehighestreactivity worthneednotbeassumedtobestuckinthefullywithdrawn position.
ST.LUCIE-UNIT13/41-27-23-81 3/4.4REACTORCOOLANTSYSTEMREACTORCOOLANTLOOPSLIMITINGCONDITION FOROPERATION 3.4.1Fourreactorcoolantpumpsshallbeinoperation.
APPLICABILITY:
Asnotedbelow,butexcluding MODE6.ACTION:MODES1and2:Withlessthanfourreactorcoolantpumpsinoperation, beipatleastHOTSTANDBYwithin6hours.MODES3,4and5:Operation mayproceedprovided(1)atleastonereactorcoolantloopisinoperation withanassociated reactorcoolantpumporshutdowncoolingpumpand(2)theSHUTOOMNMARGINrequirmnent ofSpecification 3.1.1.1isincreased toandmaintained at>5.0Sak/kduringoperation inNOOE3whenlessthanfourreactorcoolantpumpsareinoperation.
Theprovisions ofSpecifications 3.0.3and3.0.4arenotapplicable.
SURVEILLANCE REUIREMENT4.4.1TheFlowDependent SelectorSwitchshallbedetermined tobeinthe4pumppositionwithin15minutespriortomakingthereactorcriticalandatleastonceper12hoursthereafter Al1reactorcoolantpumpsandshutdowncoolingpumpsmaybede-energized forupto1hour,providednooperations arepermitted whichcouldcausedilutionofthereactorcoolantsystemboronconcentration.
ST.LUCIE-UNIT13/44-17-23-81 DESIGNFEATURES5.2.1.2SHIELDBUILDINGa.Minimumannularspace=4feet.b.Annulusnominalvolume=543,000cubicfeet.c.Nominaloutsideheight(measured fromtopoffoundation basetothetopofthedome)=230.5feet.d.Nominalinsidediameter=148feet.e.Cylinderwallminimumthickness
=3feet.f.Domeminimumthickness
=2.5feet.g.Domeinsideradius=112feet.DESIGNPRESSUREANDTEMPERATURE 5.2.2Thecontainment vesselisdesignedandshal1bemaintained foramaximuminternalpressureof44psigandatemperature of264'F.PENETRATIONS 5.2.3Penetrations throughthecontainment structure aredesignedandshallbemaintained inaccordance withtheoriginaldesignprovisions contained inSections3.8.2.1.10and6.2.4oftheFSARwithallowance fornormaldegradation pursuanttotheapplicable Surveillance Requirements.
5.3REACTORCOREFUELASSEMBLIES 5.3.1Thereactorcoreshallcontain217fuelassemblies witheachfuelassemblycontaining amaximumof176fuelrodscladwithZircoloy-4.Eachfuelrodshallhaveanaoinalactivefuellengthof136.7inchesandcontainamaximumtotalweightof2250gramsuranium.Theinitialcoreloadingshallhaveamaximumenrichment of2.83weightpercentU-235.Reloadfuelshallbesimilar-inphysicaldesigntotheinitialcoreloading.5.3.2Except,forspecialtestasauthorized bytheNRC,allfuelassemblies
.ndercontrolelementassemblies shallbesleevedwithasleevedesignpreviously approvedbytheNRC.ST.LUCIE-UNIT15-47-23-81 Two-Loop-2754 MHtTheTwoLoop-2754 MWtcasewasinitiated attheconditions listedinTable7.3.2-1.TheModerator Temperature Coefficient (MTC)ofreactivity assumedin-theanalysiscorrespondstoendoflife,sincethisnegativeMTCresultsinthegreatestpositivereactivity additionduringtheRCScooldowncausedbytheSteamLineRupture.Sincethereactivity changeassociated withmoderator feedbackvariessignificantly overthemoderator densitycoveredintheanalysis, acurveofreactivity insertion versusdensityratherthanasinglevalueofMTCisassumedintheanalysis.
Themoderator cooldowncurvegiveninFigure7.3.2-1wasconservatively calculated assumingthatonreactorscram,thehighestworthControlElementAssemblyisstuckinthefullywithdrawn position.
Thereactivity defectassociated withfueltemperature decreaseisalsobasedonendoflifeDopplerdefect.TheDopplerdefectbasedonanendoflifeFuelTemperature Coefficient (FTC),inconjunction withthedecreasing fueltemperatures, causesthegreatestpositivereactivity insertion duringtheSteamLineRuptureevent.Theuncertainty ontheFTCassumedintheanalysisisgiveninTable7.3.2-1.The8fractionassumedisthemaximumabsolutevalueincluding uncertainties forendoflifeconditions.
Thistooisconservative sinceitmaximizes subcritical multiplication andthus,enhancesthepotential forReturn-to-Power (R-T-P).TheminimumCEAworthassumedtobeavailable forshutdownatthetimeofreactortripatthemaximumallowedpowerlevelis6.74Xap.Thisavailable scramworthwascalculated forthestuckrodwhichproducedthemoderator cooldowncurveinFigure7.3.2-1.Theanalysisconservatively assumedthat,onSafetyInjection Actuation Signal,oneHiqhPressureSafetyInjection pumpfailstosta'rt.Theanalysisalsoassumedacons'ervatively lowvalueofboronreactivity worthof-1.0Ãhpper105PPM.Theconservative assumptions onfee'dwater flowwerediscussed previously.
Thefeedwater flowandenthalpyasafunctionoftimearepresented inFigures7.3.2-2and7.3.2-3respectively.
Table7.3.2-2presentsthesequenceofeventsforthefullpowercaseinitiated attheconditions giveninTable7.3.2-1.Thereactivity in-sertionasafunctionoftimeispresented inFigure7.3.2-4.TheresponseoftheNSSSduringthiseventisgiveninFigures<,3.2-5through7.3.2-9.TheresultsoftheanalysesshowthatSIASisactuatedat15seconds,atwhichtimetheReactorCoolantPumpsaremanuallytrippedbytheoperator.
ThemanualtripofRCP'sslowsdowntherateofprimaryheatremovalandthusdelaysthetimewhentheaffectedsteamgenerator blowsdry.Theaffectedsteamgenerator blowsdryat154secondsandtermi-natesthecooldownoftheRCS.Thepeakreactivity attainedpriortodeliveryofauxiliary feedwater flowis-.205Ãapat169seconds.Apeakposttrippowerofl4.0~,consisting of12.2'Xdecayheatand1.8'Xfissionpower,isproducedat72.8seconds..
Thecontinued production ofdecayheatfromthefuelaftertermination ofblowdown, causesthereactorcoolanttemperatures toincrease.
Thisinturnreducesthemagnitude ofthepositivemoderator reactivity insertedandthusthetotalreactivity becomesmorenegative.
7-23-81 Thedeliveryofauxiliary feedwater flowtotheaffectedsteamgenerator at180secondsinitiates afurthercooldownoftheRCSwhichresultsinmorepositivereactivity insertion.
However,continued additionofnegativereactivity bytheboroninjectedviatheHPSIpumppreventsthepositivereactivity insertion ofthemoderator fromcausingareturnto.criticality.'he coreremainssubcritical throughout
'heremainder ofthetransient.
TheSteamLineRuptureeventfromHFPconditions withautomatic initiation ofauxiliary feedwater andmanualtripofRCP'sonSIASshowsthatthecoredoesnotproducesignificant instantaneous fissionpower.Sincethereisnosignificant Return-to-Power, itcanbeconcluded thatcriticalheatfluxeswi-llnotheexceeded.
TwoLoo-NoLoadThetwoLoop-NoLoadcasewasinitiated attheconditions qiveninTable7.3.2-3.Themoderator cooldowncurveisgiveninFiqure7.3.2-10.
Thecooldowncurvecorresponds toanendoflifeNTC.AnendoflifeFTCwasalsousedforthereasonspreviously discussed inconnection withtheTwoLoop-2754 MWtcase.TheminimumCEAshutdownworthavailable isconservatively assumedtobetheminimumrequiredTechnical Specification limitof5.0hp.Amaximuminverseboronworthof80PPH/Rapwasconservatively assumedforthesafetyinjection duringthenoloadcase.Thefeedwater flowandtheenthalpyusedintheanalysisarepresented inFigures7.3.2-11and7.3.2-12.respectively.
>IhenallCEA'sareverifiedtobefullyinserted(duringmodes3and4)iisnotnecessary toassureone(theoneofhighestreactivity worth)isstuckinafullywithdrawn positionwhencalculating shutdownmargin.Table7.3.2-4presentsthesequenceofeventsfortheTwoLoop-NoLoadcaseinitiated fromtheconditions giveninTable7.3.2-3.Thereactivity insertion asafunctionoftimeispresented inFigure7.3.2-13.
Theresponse-ofkeyNSSSparameters during-thiseventaregiveninFigures7.3.2-'l4
'hrough7.3.2-18.
TheresultsoftheanalysisshowthatSIASisactuatedat12.0seconds,atwhichtimetheRCP'saremanuallytrippedbytheoperator.
Theaffectedsteamgenerator blowsdryat180.0seconds.Auxiliary feed-waterflowisinitiated at180.1secondswhichcontinues thecooldownoftheRCS.Thus,thetotalcorereactivity iscritical'for ashortperiodoftime.Thepeakreactivity attainedisonly+.140Kapat401.0seconds.TheadditionofboronviaHighPressureSafetyInjection mitiqates thereactivity transient.
Thecorepowerlevelremainslessthan1%ofratedpoweratalltimesduringtheevent.Sincethereisnosignificant R-T-PfortheTwoLoop-NoLoadcase,itcanbeconcluded thatthecriticalheatfluxwillnotbeexceededduringthisevent.
TABLE'7;3.2-1 KEYPARAMETERS ASSUMEDINTHESTEAMLINERUPTUREANALYSIS2-LOOP-2754 MWTParameter InitialCorePowerInitialCoreInletTemperature InitialRCSPressureInitialCoreMassFlowRateInitialSteamGenerator PressureMinimumCEAWorthAvailable atTrip~..Doppler.Multiplier Moderator CooldownCurveInverseBoronWorthEffective FullPowerMTCgFraction(including, uncertainties)'ni tsoFpslax10ibm/hrps1aCapvs.densityPPM/Xnpx10ap/FReference CcIe*27545512300'33.8'909W.251.15SeeFigure7.3.2-1105-25.0060~Ccie527545512300133.8900-6.741.15SeeFigure7.3.2-1105<<2e2.0060*(Note:Thelastcompleteblowdown.
analysisforthiseventwasperformed fortheCycle4stretchpowersubmittal.)
TABL'E7.3;2-2SEQUENCEOFEVENTSFORSTEAMLINERUPTUREEVENTWITHAUTOMATIC INITIATION OFAUXILIARY FEEDWATER ANDMANUALTRIPOFREACTORCOOLANTPUMP2-LOOP-2754 MWTTimesec)0.02.32.3.Qo23.2EventSteamLineRuptureOccursLowSteamGenerator PressureTripSignalOccursMainSteamIsolation Signalgenerated MainSteamIsolation ValvesBegintoClose,TripBreakersOpenSetointorValue578psia578psia3.7'9.214.615.015.045.063.372.8154.5'69.0 180.0600.0CEAsBegintoDropintoCoreMainSteamIsolation ValvesCompletely ClosedPressurizer Empties:SafetyInjection Actuation SignalReactorCoolantPumpsManuallyTrippedHighPressureSafetyInjection PumpsStartHainFeedwater Isolation PeakPost.TripPowerAffectedSteamGenerator BlowsDryPeakReactivity, PriortoAuxiliary Feedwater FlowAuxiliary Feedwater FlowInitiated toRupturedSteamGenerator OperatorIsolatesRupturedSteamGenerator andTerminates Auxiliary Feedwater Flow1578.0psia14.05-.205'ap253.6ibm/sec7-23-81 Isss'TABLE'7;3;2-3 KEYPARAMETERS ASSUMEDINTHESTEAMLINERUPTUREANALYSIS2-LOOP,NOLOADParameter InitialCorePowerInitialCoreInletTemperature InitialRCSPressureInitialSteamGenerator PressureMinimumCEAWorthAvailab1eatTripDopplerMultiplier Moderator CooldownCurveInverseBoron1<orthEffective FullPowerMTC.gFracti.on (including uncertainty)
UnitsMWt'oFpsiapsiaCapvs.densityPPM/lap10ap/FReference
~Ccle*1.05322300'00-4.31.15SeeFigure7.3.2-10100-28'0060~Cele51.05322300900-5.00;85SeeFigure7.3.2-10802%2.0060.*Cycle4stretchpowersubmittal 7-23-81 TABLE7;3.2-4SEQUENCEOFEVENTSFORSTEAMLiNERUPTUREEVENTWITHAUTOMATIC INITIATION OFAUXILIARY FEEDWATER ANDMANUALTRIPOFREACTORCOOLANTPUMPS2-LOOP,NOLOADTimesec0.03.8.3.84.74.75.210.210.712.0'2.042.086.0180.0180.1401.0520.0600.0EventSteamLineRuptureOccurs'ILowSteamGenerator PressureTripSignalOccursMainSteamIsolation, SignalGenerated MainSteamIsolation ValvesBegintoCloseTripBreakersOpenCEAsBegintoDropIntoCorePressurizer EmptiesMainSteamIsolation ValvesCompletely ClosedSafety.Injection Actuation SignalReactorCoolantPumpsManuallyTrippedHighPressureSafetyInjection PumpsStartHainFeedwater Isolation AffectedSteamGenerator BlowsDryAuxiliary Feedwater FlowInitiated toRupturedSteamGenerator PeakReactivity ReturntoPowerOperatorIsolatesRupturedSteamGenerator andTerminates Auxiliary Feedwater FlowSetointorValue578.0psia578.0psia1578.0psia253.6ibm/sec+e140Xapc15ofratedpower7-23-81 2LOOP-FULL PONERCYCLEIICYCLE50QO5055DENSITY;LBi'l/CUBIC FT60657-23-81FLORIDAPOWER8.LIGHTCo.St.LuciePfantSTEAMLINEBREAKEVENTMODERATOR REACTIVIT'(
FEEDBACKvsunnco<Tnonet,c:TT'4
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+10002LOOP-FULL POWER+8COI-+600g+000+200UNAFFECTED SG0-.ZOO0100AFFECTEDSG200300L}00TIf'lE,SECONDS600FLORIDAPOWER8LIGHTgOSt.LuciePlantUnitlSTEAMLINE8REAKEVENTSTEAMGENERATOR PRESSURES vsTIME7-23-817,5,2-9 5.02LOOP-NOLOAD3.0~I-2.0CDl81.0CYCLE0CYCLE550.05S.Ot,'o.o65.0INODERATOR DENSITY,LBN/FT7-23-81FLORIDAPO%'ER8LIGHTCO.St.LuciePIontiS~~~STEAMLINERUPTUREQ(ENTMODERATOR R'ACTIVITY vsMOD"RATORDENSITYFigure7.3.2-10
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