ML17320B075

Proposed Tech Spec Changes Re Addl Limitation on Nuclear Enthalpy Rise Hot Channel Factor Due to New Loca/Eccs Analysis in Support of Cycle 5 Reload

ML17320B075
Person / Time
Site:	Cook
Issue date:	05/21/1984
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
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ML17320B074	List: ML17320B073 ML17320B075
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NUDOCS 8405290296
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Table2.1O.C.CookUnit2l.OCA/ECCS AnalysisSu@naryResultsfortheCcle5CoreConfiuration85$ENCFuelPeakRodAverage8urnup(HMD/kg)FTQTPeakCladdingTemperature (oF)MaximumLocalEr-H20Reaction(5)TotalZr-H20Reaction2.02.041.41521987.4<1.010.02.041.41521907.3<1.047.02.041.415'20965.7(1.0:g4OS2eO29 GSOOOSfb""

'g@40521'",<<,",

'",.),,pgp'PDGCK,,pGp'..',:p~

~~i-1p'llL'i1 Table3.21.0DECLGBreakAnalysisParameters PeakRodAverageBurnup(HID/kg)TotalCorePower(NMt)*TotalPeaking(F~)TFractionEnergyDeposited inFuel~FullyModerated Core~VoidedCore2.034112.040.9740.95410.034112.040.9740.95447.034112.040.9740.954Ccle585%ENCFuel)Peaking~AxialxEngineering

~EnthalpyRise(F~H)T1.4421.4151.4421.415l.4421.415*2%poweruncertainty isaddedtothisvalueintheLOCAanalysis.

Table3.41.0DECLGBreakFuelResponseResultsforCycle5PeakRodAverageBurnup(NMD/kg)InitialPeakFuelAverageTemperature (oF)HotRodBurst~Time(sec)~Elevation (ft)~ChannelBlockageFractionPeakCladTemperature

~Time(sec)~Elevation (ft)~Temperature (oF)Zr-SteamReaction~LocalMaximumElevation (ft)~LocalMaximum(g)*~CoreMaximum2.0215160.96.50.242278.6321988.637.4<1.010.0206061.76.50.272278.6321903.637.3<1.047.0162967.97.00.472418.8820968.885.7<1.0*Values400secintoLOCAtransient.

iFQ~2-0IiF~1.<150RePNQO/KGPCTHODE(HOOE14ATI.CtFT.lt-RLN'THEOHOOE(HOOE5ATC.$0FT-)IClClgQ,~d44.0e0.0Lt0.01400t000t)00tt04TIHE-SE'CONDS%0.0)Cl.~Fiqure3.41TOODEE2CladdingTemperature versusTime,1.0DECLGBreak,2.MWD/KgCase iFQ~R,.04iFOH~1'15DRi 17HW/K1.PCTHODEtNOK1$ATl.lfFT.)t.MTQKt)NSEtHOOEu.AT1.00FT)44.0t0.0tt0.0iC0.05$.0t.td0TIHE'SECONDSS0.0050Xb.~ci~nr~l4RTOODEE2CladdinoTemperature versusTime,1.0DECLGBreak,47.MWD/KgCase

>FW2.04oFOWl.<150Ro10HNOIK1..PCTNHKfNODE19ATa.etFT.)t-RLPTllKDt400E(HATE0AT0.$0FT.)i0.0e0.41t0.0140.0'O0.0t40.0TINE-SECONDStl0.4KJt.0~-~Figure3.42TOODEE2CladdingTemperature versusTime,1.0DECLGSreak,10.NWD/KgCase Mr.Haro1dR.Den<<4AEP:NRC:0860KATTACHMENT 2PROPOSEDREVISIONTOTECHNICAL SPECIFICATION PAGES CSFLORATEANDNUCEARENTYE00ERATIO3.2.3Thecombination ofindicated ReactorCoolantSystem(RCS)totalflowrateandRshallbemaintained withintheregionofallowable operation shownonFigures3.2-4and3.2-5for4and3loopoperation, respectively.

For:Westinghouse FuelNAHR-"-f1.48[1.0+0.2(1.0-P)]for:ExxonNuclearCompanyFuelNWWWWO~WW&W&W&WWW WWWWWOWWWWR=1.49[1.0+0.2(1.0-P)]And,F<H51.36/PforExxonNuclearCompanyFuelNwhere:RATEDTHERMALPOWERandFAHN=measuredvaluesofF<obtainedbyusingthemovableNincoredetectors toob$ainapowerdistribution map.ThemeasuredvaluesofF~andflow,withoutadditonal uncertainty allowance, shallbeusedtocomparewithlimits.fZZLIQAPXJJX'QXXQK MODE1.NWithFAHabovetheallowable limitorwiththecombination ofRCStotalflowrateandRoutsidetheregionofacceptable operation shownonFigure3.2-4or3.2-5(asapplicable):

a~Within2hours:l.EitherrestoreFAandthecombination ofRCStotalflowNrateandRtowithPntheabovelimits,or2.ReduceTHERMALPOWERtolessthan50$ofRATEDTHERMALPOWERandreducethePowerRangeNeutronFlux-HightripsetpointtoJ55$ofRATEDTHERMALPOWERwithinthenext4hours.D.C,COOK-UNIT23/42-9AMENDMENT NO.

kGXZQK:(Continued) b.Within24hoursofinitially beingoutsidetheabovelimits,verifythroughincorefluxmapp1ngandRCStotalflowratecompar1aon thatF$Eandthecomhinatlon ofRandROEtotalflowratearerestored%owithintheabovelimits,orreduceTHERMALPOWERtolessthan5$ofRATEDTHERMALPOWERwithinthenext2hours.c~Identifyandcorrectthecauseoftheout-of'-limit condition priortoincreasing THERMALPOWERabovethereducedTHERMALPOWERLimitrequiredbyACTIONitemsa.2and/orbabove;subsequent POWEROPERATION mayproceedprovfdedthatF)andthecombination ofRandindicated RCStotalflowratearedemonstrated, throughincorefluxmappingandRCStotalflowratecomparison, tobewithinthereg1onofacceptable operation asdefinedaboveforF"andasshownonFigure3.2-4or3.2-5(asapplicable) forRCSflowrateandRpriortoexceed1ng thefollowing THERMALPOWERlevels:1.Anominal501ofRATEDTHERMALPOWER,2.Anominal75$ofRATEDTHERMALPOWER,and3.Within24hoursofattaining g954ofRATEDTHERMALPOWER.4.2.3.1Theprovisions ofSpecif1cation 4.0.4arenotapplicable.

N'.2.3.2F<Hshallbedetermined tobewithintheabovelimitsandthecombination ofindicated RCStotalflowrateandRshallbedetermined tobewithintheregionofacceptable operation ofFigure3.2-4or3.2-5(asapplicable):

a.Priortooperat1on above75$ofRATEDTHERMALPOWERaftereachfuelloading,andb.Atleastonceper31Effective FullPowerDays.4.2.3.3TheRCStotalflowrateindicators shallbesub)ected toaCHANNELCALIBRATION atleastonceper18months.4.2.3.4TheRCStotalflowrateshallbedetermined bymeasurement atleastonceper18months.D.C.COOK-UNIT23/42-10AMENDMENT NO.

~~4846eMeasurement Uncertainties of3.5%forFlo~and4%FJHareaccounted forintheanalysiswhichsupportsthisFigure.4442C)440[ACCEPTABLE OPERATION REGION~~~=-=--=-'=-:-UNACCEPTABLE OPERATION REGION(0.3=,:i.

77).340.900.940.981.021.06R*F~NH/1.

48[1.0+0.

2(l.0-P)lWESTINGHOUSE FUELR*FNH/1.49{1.0 0.2(1.0-P)]

EXXONNUCLEARCO.FUEFIGURE3.24RCSTOTALFlO'NRATEVERSUSRFOURLOOP5INOPERATION a~a<0.C.COOKUNIT23/42-11Amendment No.~~

~~3634XCL,CD32'Htasureaent Unclrtalnt)es:

.'of3.5%forFlowandi%..<orFareaccounted for.:intheanalysiswhich,supportsthisFigure.0~~A~ACCEPTAgLE OPERATION REGION~~~Ktshouldbenotedthatthreeloooooerat'on usingthiscurseisnotcurrenlyallowedNechangescontained inthistableareforReference only.~Ii~~~~C730IC)28(~UNACCEPTAgLE

~OPERAT'ON

~'"IGt'~','..0,27.13)

Z6=::.(0.971,26.'.=.)

240.900.940.981.021.061.1014R<F"H/l.48{1.0+0.2(1.0-P)]MESNGHOUSEFUELR*F"H/1.49{1.0+0.2(I.O-P)

]EXXONNUCLEARCO.FUELFIGURE3.2-5RCSTOTALFLOQRATEVERSUSR-THREELOOPSINOPERATION 0.C.COOKUNIT23/42-12Apgn4nent No.

Thecurvesarebasedonanuclearenthalpyrisehotchannelfactor,p,ori.49andareference cosinewithapeakoft.55i'oraxialpowershape.Anallowance isincludedforanincreaseinF<HatreducedpowerbasedAH'ntheexpression:

F>H-1.48[1+0.2(1-P)](Westinghouse Fuel)F<H=1.49[1+0.2(1-P)](ExxonNuclearCompanyFuel)NwherePisthefractionofRATEDTHERMALPOWER.Theselimitingheatfluxconditions arehigherthanthosecalculated fortherangeofallcontrolrodsfullywithdrawn tothemaximumallowable oontrolrodinsertion assumingtheaxialpowerimbalance iswithinthelimitsofthef(AI)functionoftheOvertemperature trip.Whentheaxialpowerimbalance iknotwithinthetolerance, theaxialpowerimbalance effectontheOvertemperature ATtripswillreducethesetpoints toprovideproteotion consistent withcoresafetylimits.ForExxonNuclearCompanysuppliedfuel,anadditional limitation onF<isappliedtoensurecompliance withECCSacceptance criteria.

Thislimitation isdiscussed inbasissection3/4.2.2and3/4.2.3anddoesnotaffectthesafetylimitcurve.2.1.20CTherestriction ofthisSafetyLimitprotectstheintegrity oftheReactorCoolantSystemfromoverpressurization andtherebypreventsthereleaseofradionuclides contained inthereactorcoolantfromreachingthecontainment atmosphere.

Thereactorpressurevesselandpressurizer aredesignedtoSectionIIIoftheASMECodeforNuclearPowerPlantwhichpermitsamaximumtransient pressureof110$(2735psig)ofdesignpressure.

TheReactorCoolantSystempiping,valvesandfittings, aredesignedtoANSIB31.11967Edition,whichpermitsamaximumtransient pressureof120%(2985psig)ofcomponent designpressure.

TheSafetyLimitof2735psigistherefore consistent withthedesigncriteriaandassociated coderequirements.

TheentireReactorCoolantSystemishydrotested at3107psig,125$of'designpressure, todemonstrate integrity priortoinitialoperation.

D.C.COOK-UNIT2B2-2AMENDMENT NO.

Thespecifications of'hissectionprovideassurance offuelintegrity duringCondition I(NormalOperation) andII(Incidents ofModerateFrequency) eventsby:(a)maintaining thecalculated DNBRinthecoreatorabovedesignduringnormaloperation andinshorttermtransients, and(b)limitingthefissiongasrelease,fuelpellettemperature andoladd1ngmechan1cal properties towithinassumeddesigncriteria.

Inadd1tion, limitingthepeaklinearpowerdensitydur1ngCondition Ieventsprovidesassurance thattheinitialcond1t1ons assumedf'rtheLOCAanalysesaremetandtheECCSacceptance criterialimitof2200Fisnotexceeded.

Thedefinitions ofcertainhotohannelandpeakingfactorsasusedinthesespecifications areasfollows:F(Z)HeatFluxHotChannelFactor,isdefinedasthemaximumlocalheatfluxonthesurfaceof'fuelrodatcoreelevation Zdividedbytheaveragefuelrodheatflux,allowingformanufacturing tolerances onfuelpelletsandrods.NFAHNuclearEnthalpyRiseHotChannelFaotor,isdefinedastheratiooftheintegraloflinearpoweralongtherodwiththehighestintegrated powertotheaveragerodpower.NThelimitsonF(Z)andF<forWestinghouse suppliedfuelatacore-averagepowerof3431MWtare1.$7and1.48,respectively, whichassureconsistency withtheallowable heatgeneration ratesdeveloped foracoreaveragethermalpowerof3391MWt.ThelimitsonF(Z)andF".forENCsuppliedfuelhavebeenestablished forgcorethermalpoweroP3411MWt.ThelimitonF(Z)is2.04.ThelimitonF>is1.36forLOCA/ECCS analysisand1.49forDIIBanalyses.

Theanalysessupporting theExxonNuclearCompanylimitsarevalidforanaveragesteamgenerator tubepluggingofupto5$andamax1mumpluggingofoneormoresteamgenerators ofupto10$.Inestablishing thelimits,aplantsystemdescription withimprovedaccuracywasemployedduringtherefloodportionoftheLOCATransient.

WithrespecttotheWestinghouse suppliedfueltheminimumproJected excessmarginofatleast10$toECCSlimitswillmorethanoffsettheimpactofincreasesteamgenerator tubeplugging.

ThelimitsonAXIALFLUXDIFFERENCE assurethattheF(Z)upperboundenvelopeisnotexceededduringeithernormaloperation oFintheeventofxenonredistribution following powerchanges.TheF(Z)upperboundenvelopeis1.97timestheaveragefuelrodheatfluxforWeslinghouse suppl1edfueland2.04t1mestheaveragefuelrodheatfluxforExxonNuclearCompanysuppliedfuel.Targetfluxdifference isdetermined atequilibrium xenonconditions.

Thefulllengthrodsmaybepositioned withinthecoreinaccordance withtheirrespective insertion limitsandshouldbeinsertednearthe1rnormalposit1onforsteadystateoperation athighpowerlevels.ThevalueoftheD.C.COOK-UNIT2B3/42-1AMENDMENT NO.

2HEATLOTCTOThelimitsonheatfluxhotchannelfactor,RCSflowrate, andnuclear,enthalpyrisehotchannelfactorensurethat1)thedesignlimitsonpeaklocalpowerdensityandminimumDNBRarenotexceededand2)$ntheeventofaLOCAthepeakfuelcladtemperature willnotexceedthe2200FECCSacceptance criterialimit.Eachoftheseismeasurable butwillnormallyonlybedetermined periodically asspecified inSpecifications 0.2.2and4.2.3.Thisperiodicsurveillanoe issufficient toensurethatthelimitsaremaintained provided:

a.Controlrodsinasinglegroupmovetogetherwithnoindividual rodinsertion differing bymorethan+12stepsfromthegroupdemandposition.

b.Controlrodgroupsaresequenced withoverlapping groupsasdescribed inSpecification 3.1.3.6.c.Thecontrolrodinsertion limitsofSpecifications 3.1.3.5and3.1.3.6aremaintained.

d.Anditionallimitation onF<appliestoExxonNuolearCompanyfuel.NThisF<Hlimit,incombination witktheF~(Z)limit,ensurescompliance withtheECCSacceptance criteria.

Anallowance isincludedforanincreaseinF<Hatreducedpowerbasedonthefollowing expression:

NTheaxialpowerdistribution, expressed intermsofAXIALFLUXDIFFERENCE, ismaintained withinthelimits,NF<Hwillbemaintained withinitslimitsprovidedoonditions a.throughd.abovearemaintained.

AsnotedonFigures3.2-4and3.2-5,RCSflowrateandF<maybe"tradedoff"againstoneanother(i.e.,alowmeasuredRCSflowra@isacceptable ifthemeasuredF<isalsolow)toensurethatthecalculated DNBRwillnotbebelowthebesign DNBRvalue.Therelaxation ofF<HasafunctionofTHERMALPOWERallowschangesintheradialpowershapeforallpermissible rodinsertion limits.Theformofthisrelaxation forDNBRlimitsisdiscussed inSection2.1.1ofthebasis.F<Ng1.36/P(ExxonNuclearCompanyFuel)where:PisthefractionofRATEDTHERMALPOWER.Thepowerdependence ofthisallowance is1/Pbecausetheassooiated F<Hlimitof136resultsfromtheLOCAanalysis.

Themorerestrictive oftheflowdependent DNBRF<HlimitandtheLOCANF~limitforExxonNuclearFuelCompanyfuelmustbeapplied.D.C.COOK-UNIT2B3H2-4AMENDMENT NO.

RISER-(Continued)

F~reB3/42-2illustrates theimplementat1on ofthelimitsasafnctioofpower.AmeasuredflowwillresultinalimitingvalueforRwhichmustbeobtainedfromFigure3.2-4orFigure3.2<<5.FromthislimitingR,alimitingF<Hcanbeobtainedbecause:Westinghouse FuelF>H=1.48XRX[1.0+0.2(1.0-P)3, ExxonNuclearCompanyFuelFAH=1.49XRX[1.0+0.2(1.0-P)]

Where:PTHERMALPOWERRATEDTHERMALPOWERFigureB3/42-2displaystwolimitiggDNBRFcurvesfearExxonNuclearNCompanyfuelforflowsof36.77X10cpm,an37.63X10gpm.Alsodisplayed onFigureB3/42-2isthelimitoqF<HwhichresultsfromtheLOCAanalys1si'orExxonNuclearCompanyfueQpmustbemaintaiyd belowandtotheleftofboththeapplicable DNBRF<HlmIItandtheLOCAF<Hlimit.ForWestinghouse fuelthere1sonlyoneglimit.Itrustbeobtained-Nfromtheapplicable relationships amongR,F<H,P,andflow.WhenanFmeasurement istaken,bothexperimental errorandmanufacturing tolerance mustbeallowedfore5gistheappropriate allowance forafullcoremaptakenwiththeincoredetectorfluxmappingsystemand3$istheappropriate allowance formanufactur1ng tolerance.

WhenRCSflowrateandF<aremeasured, noadditional allowances.

areNnecessary priortocomparison 4ththelimitsofSpecif1cat1on 3.2.3.Measurement errorsof3.5$forRCSflowtotalflowrateand4$forFN<Hhavebeenallowedforindetermination ofthedesignDNBRvalueandinthedeterm1nation oftheLOCA/ECCS limit.D.C.COOK-UNIT2B3/42-4aAMENDMENT NO.

0&&1.65&~&'.4~~-~~1.55&Opium+~~~&~I.35020406080PERCENTOFRATEDTHERMALPOWER100FIGUREB3/42-2ILLUSTRATIVE EXAMPLEOFF~HLIMITVERSUSPERCENTTHERMALPOWERFOREXXONFUELB3/42-4b