ML17328A563

Proposed Tech Specs Re Implementation of Core Operating Limits Rept,Per Generic Ltr 88-16

ML17328A563
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Site:	Cook
Issue date:	02/06/1990
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
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ML17328A562	List: ML17328A561 ML17328A563
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GL-88-16, NUDOCS 9002140165
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Attachment 2TOAEP;NRC:1077A PROPOSEDTECHNICAL SPECIFICATION CHANGESnvocv~pp~p+pzPK05ppppPgg INDEXDEFINITIONS SECTIONPAGE1.0DEFINITIONS Solidification OffsiteDoseCalculation Manual(ODCM)GaseousRadwasteTreatment SystemVentilation ExhaustTreatment SystemPurge-Purging VentingMember(s)

OfThePublicSiteBoundaryUnrestricted AreaAllowable PowerLevelCoreOperating LimitsReport(COLR)Operational Modes(Table1.1)Frequency Notation(Table1.2)1-71-71-71-7'-71-71-81-81-81-81-81-91-10COOKNUCLEARPLANT-UNIT2AMENDMENT NO~

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DEFINITIONS.

MEMBERSOFTHEPUBLIC1.35MEMBER(S)

OFTHEPUBLICshallincludeallpersonswhoarenotoccupationally associated withthePlant.Thiscategorydoesnotincludeemployees oftheutility,itscontractors oritsvendors.Alsoexcludedfromthiscategoryarepersonswhoenterthesitetoserviceequipment ortomakedeliveries.

Thiscategorydoesincludepersonswhouseportionsofthesiteforrecreational, occupational orotherpurposesnotassociated withthePlant.SITEBOUNDARY1.36TheSITEBOUNDARYshallbethatlinebeyondwhichthelandisnotowned,leasedorotherwise controlled bythelicensee.

UNRESTRICTED AREA1.37AnUNRESTRICTED AREAshallbeanyareaatorbeyondtheSITEBOUNDARYtowhichaccessisnotcontrolled bythelicenseeforpurposesofprotection ofindividuals fromexposuretoradiation andradioactive materials oranyareawithinthesiteboundaryusedforresidential quartersorindustrial, commercial, institutional and/orrecreational purposes.

ALLOWABLE'OWER LEVELAPL1.38APLmeans"allowable powerlevel"'hich isthatpowerlevel,lessthanorequalto100%RATEDTHERMALPOWER,atwhichtheplantmaybeoperatedtoensurethatpowerdistribution limitsaresatisfied.

COREOPERATING LIMITSREPORTCOLR1.39TheCOLRistheunit-specific documentthatprovidescoreoperating limitsforthecurrentoperating reloadcycle.Thesecycle-specifc coreoperating limitsshallbedetermined foreachreloadcycleinaccordance withSpecification 6.9.1.11.

Unitoperation withintheseoperating limitsisaddressed inindividual specifications.

COOKNUCLEARPLANT-UNIT21-8AMENDMENT NO.

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SAFETYLIMITSBASESThecurvesarebasedonanuclearenthalpyrisehotchannelfactor,definedintheCOLRandareference cosinewithapeakof1.55foraxialpowershape.Anallowance isincludedforanincreaseinF"atreducedpowerbasedontheexpression:

F~-CFDH[1+PFDH(1-P)]where:CFDHistheFHlimitatRTPspecified intheCOLRAHPFDHisthepowerfactormultiplier forF~providedintheCOLRPisthefractionofRATEDTHERMALPOWERTheselimitingheatfluxconditions arehigherthanthosecalculated fortherangeofallcontrolrodsfullywithdrawn tothemaximumallowable controlrodinsertion assumingtheaxialpowerimbalance iswithinthelimitsofthefl(AI)functionoftheOvertemperature trip.Whentheaxialpowerimbalance isnotwithinthetolerance, theaxialpowerimbalance effectontheOvertemperature ATtripswillreducethesetpoints toprovideprotection consistent withcoresafetylimits.2.1.2REACTORCOOLANTSYSTEMPRESSURETherestriction ofthisSafetyLimitprotectstheintegrity oftheReactorCoolantSystemfromoverpressurization andtherebypreventsthereleaseofradionuclides contained inthereactorcoolantfromreachingthecontainment atmosphere.

iThereactorpressurevesselandpressurizer aredesignedtoSectionIIIoftheASMECodeforNuclearPowerPlantwhichpermitsamaximumtransient pressureof110%(2735psig)ofdesignpressure.

TheReactorCoolantSystempiping,valvesandfittings, aredesignedtoANSIB31.11967Edition,whichpermitsamaximumtransient pressureof1208(2985psig)ofcomponent designpressure.

TheSafetyLimitof2735psigistherefore consistent withthedesigncriteriaandassociated coderequirements.

TheentireReactorCoolantSystemishydrotested at3107psig,125%ofdesignpressure, todemonstrate integrity priortoinitialoperation.

COOKNUCLEARPLANT-UNIT2B2-2AMENDMENT NO.

1~Ar.V>1t REACTIVITY CONTROLSYSTEMSMODERATOR TEMPERATURE COEFFICIENT LIMITINGCONDITION FOROPERATION 3.1.1.4Themoderator temperature coefficient (MTC)shallbewithinthelimitsspecified intheCOLR.ThemaximumupperlimitshallbelessthanorequaltothelimitshowninFigure3.1-2.APPLICABILITY:

-BOLLimit-MODES1and2*only¹'OLLimit-MODES1,2and3only¹ACTION:a~WiththeMTCmorepositive, thantheBOLlimitspecified intheCOLR:l.Establish andmaintaincontrolrodwithdrawal limitssufficient torestoretheMTCtowithinitslimitwithin24hoursorbeinHOTSTANDBYwithinthenext6hours.Thesewithdrawal limitsshallbeinadditiontotheinsertion limitsofSpecification 3.1.3.6.2.Maintainthecontrolrodswithinthewithdrawal limitsestablished aboveuntilsubsequent measurement verifiesthattheMTChasbeenrestoredtowithinitslimitfortheallrodswithdrawn condition.

PrepareandsubmitaSpecialReporttotheCommission pursuanttoSpecification 6.9.2within10daysdescribing thevalueofthemeasuredMTC,theinterimcontrolrodwithdrawal limitsandthepredicted averagecoreburnupnecessary forrestoring thepositiveMTCtowithinitslimitfortheallrodswithdrawn condition.

WiththeMTCmorenegativethantheEOLlimitspecified intheCOLR,beinHOTSHUTDOWNwithin12hours.*WithKfgreaterthanorequalto1.0¹SeeSpecialTestException 3.10.3effCOOKNUCLEARPLANT-UNIT2AMENDMENT NO.

1Iit4 REACTIVITY CONTROLSYSTEMSSURVEILLANCE REUIREMENTS 4.1.1.4.1 TheMTCshallbedetermined tobewithinitslimitsbyconfirmatory measurements.

MeasuredMTCvaluesshallbeextrapolated and/orcompensated topermitdirectcomparison withtheabovelimits.4.1.1.4.2 TheMTCshallbedetermined tobewithinitslimitsduringeachfuelcycleasfollows:a)TheMTCshallbemeasuredandcomparedtotheBOLlimitspecified intheCOLRpriortoinitialoperation above5%ofRATEDTHERMALPOWER,aftereachfuelloading.b)TheMTCshallbemeasuredatanyTHERMALPOWERwithin7EFPDafterreachinganequilibrium boronconcentration of300ppm.Themeasuredvalueshallbecomparedtothe300ppmsurveillance limitspecified'in theCOLR.Intheeventthiscomparison indicates thattheMTCwillbemorenegativethantheEOLlimit,theMTCshallberemeasured atleastonceper14EFPDduringtheremainder ofthefuelcycleandtheMTCvaluecomparedtotheEOLlimit.COOKNUCLEARPLANT-UNIT23/41-6AMENDMENT NO~

~pREACTIVITY CONTROLSYSTEMSLIMITINGCONDITION FOROPERATION Continued c)Apowerdistribution mapj,sobtainedfromthemovableincoredetectors andF(Z)andF<areverifiedtobewithintheirlimitswithin79hours,'n5 d)e)EithertheTHERMALPOWERlevelisreducedtolessthanorequalto75%ofRATEDTHERMALPOWERwithinonehourandwithinthenext4hoursthehighneutronfluxtripsetpointisreducedtolessthanorequalto85$ofRATEDTHERMALPOWER,orITheremainder oftherodsinthegroupwiththeinoperable rodarealignedtowithin+12stepsoftheinoperable rodwithinonehourwhilemaintaining therodsequenceandinsertion limitsasspecified intheCOLR;theTHERMALPOWERlevelshallberestricted pursuanttoSpecification 3.1.3.6duringsubsequent operation.

SURVEILLANCE REUIREMENTS j4.1.3.1.1

'Thepositionofeachfulllengthrodshallbedetermined tobewithinthegroupdemandlimitbyverifying theindividual rodpositions atleastonceper12hoursexceptduringtimeintervals whentheRodPositionDeviation Monitorisinoperable, thenverifythegrouppositions atleastonceper4hours.4.1.3.1.2 Eachfulllengthrodnotfullyinsertedinthecoreshallbedetermined tobeOPERABLEbymovementofat'east8stepsinanyonedirection atleastonceper31days.COOKNUCLEARPLANT-UNIT23/41-19AMENDMENT NO.

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REACTIVITY CONTROLSYSTEMSRODDROPTIMELIMITINGCONDITION FOROPERATION 3.1.3.4Theindividual fulllength(shutdown andcontrol)roddroptimefromthefullywithdrawn position(specified intheCOLR)shallbelessthanIorequalto2.2secondsfrombeginning ofdecayofstationary grippercoilvoltagetodashpotentrywith:a.Tgreaterthanorequalto541F,and0avgb.Allreactorcoolantpumpsoperating.

APPLICABILITY:

MODES1AND2ACTION:Withthedroptimeofanyfulllengthroddetermined toexceedtheabovelimit,restoretheroddroptimetowithintheabovelimitpriortoproceeding toMODE1or2.SURVEILLANCE REUIREMENTS 4.1.3.4Theroddroptimeoffulllengthrodsshallbedemonstrated throughmeasurement priortoentering, MODE2:a.Forallrodsfollowing eachremovalofthereactorvesselhead,b.Forspecifically affectedindividual rodsfollowing anymaintenance onormodification tothecontrolroddrivesystemwhichcouldaffectthedroptimeofthosespecificrods,andc.Atleastonceper18months.COOKNUCLEARPLANT-UNIT23/41-23AMENDMENT NO.

REACTIVITY CONTROLSYSTEMSSHUTDOWNRODINSERTION LIMITLIMITINGCONDITION FOROPERATION 3.1.3.5Allshutdownrodsshallbelimitedinphysicalinsertion asspecified intheCOLR.APPLICABILITY:

MODES1*and2*¹ACTION:Withamaximumofoneshutdownrodinsertedbeyondtheinsertion limitspecified intheCOLR,exceptforsurveillance testingpursuanttoSpecification 4.1.3.1.2, withinonehoureither:a.Restoretherodtowithintheinsertion limitspecified intheCOLR,orb.Declaretherodtobeinoperable andapplySpecification 3.1.3.1.SURVEILLANCE REUIREMENTS 4.1.3.5Eachshutdownrodshallbedetermined tobewithintheinsertion limitspecified intheCOLR:a.Within15minutespriortowithdrawal ofanyrodsincontrolbanksA,B,CorDduringanapproachtoreactorcriticality, andb.Atleastonce.per12hoursthereafter.

• SeeSpecialTestExceptions 3.10.2and3.10.3.¹WithKffgreaterthanorequalto1.0effCOOKNUCLEARPLANT-UNIT23/41-24AMENDMENT NO.

~~REACTIVITY CONTROLSYSTEMSCONTROLRODINSERTION LIMITSLIMITINGCONDITION FOROPERATION 3.1.3.6Thecontrolbanksshallbelimitedinphysicalinsertion asspecified intheCOLR.APPLICABILITY'ODES 1*and2*¹.ACTION:Withthecontrolbanksinsertedbeyondtheinsertion limits,exceptforsurveillance testingpursuanttoSpecification 4.1.3.1.2; either:a.Restorethecontrolbankstowithinthelimitswithintwohours,orb.ReduceTHERMALPOWERwithintwohourstolessthanorequaltothatfractionofRATEDTHERMALPOWERwhich,isallowedbythegrouppositionusingtheinsertion limitsspecified intheCOLR,orc.BeinatleastHOTSTANDBYwithin6hours.SURVEILLANCE REUIREMENTS 4.1.3.6Thepositionofeachcontrolbankshallbedetermined tobewithintheinsertion limitsatleastonceper12hoursexceptduringtimeintervals whentheRodInsertion LimitMonitorisinoperable, thenverifytheindividual rodpositions atleastonceper4hours.*SeeSpecialTestExceptions 3.10.2and3.10.3¹WithKffgreaterthanorequalto1.0.effCOOKNUCLEARPLANT-UNIT23/41-25AMENDMENT NO.

~~Thispageintentionally leftblank.COOKNUCLEARPLANT-UNIT23/41-26AMENDMENT NO.

'Pljl, 3.4.2POWERDISTRIBUTION LIMITSAXIALFLUXDIFFERENCE AFDLIMITINGCONDITION FOROPERATION 3.2.1Theindicated AXIALFLUXDIFFERENCE (AFD)shallbemaintained withinthetargetbandaboutatargetfluxdifference.

Thetargetbanisspecified intheCOLR.APPLICABILITY:

MODE1above50%RATEDTHERMALPOWER*ACTION:Withtheindicated AXIALFLUXDIFFERENCE outsideofthetargetbandaboutthetargetfluxdifference andwithTHERMALPOWER:1.Above90%or0.9xAPL(whichever isless)ofRATEDTHERMALPOWER,within15minutes:a)Eitherrestoretheindicated AFDtowithinthetargetbandlimits,orb)ReduceTHERMALPOWERtolessthan90%or0.9xAPL(whi'chever isless)ofRATEDTHERMALPOWER.2.Between50%and90%or0.9xAPL(whichever isless)ofRATEDTHERMALPOWER')POWEROPERATION maycontinueprovided:

1)Theindicated AFDhasnotbeenoutsideofthetargetbandformorethan1hourpenaltydeviation cumulative duringtheprevious24hours,and2)Theindicated AFDiswithinthelimitsspecified intheCOLR.Otherwise, reduceTHERMALPOWERtolessthan50%ofRATEDTHERMALPOWERwithin30minutesandreducethePowerRangeNeutronFlux-High TripSetpoints tolessthanorequalto55%ofRATEDTHERMALPOWERwithinthenext4hours.b)Surveillance testingofthePowerRangeNeutronFluxChannelsmaybeperformed pursuanttoSpecification 4.3.1.1.1 providedtheindicated AFDismaintained withinthelimitspecified intheCOLR.Atotalof16hoursoperation maybeaccumulated withtheAFDoutsideofthetargetbandduringthistestingwithoutpenaltydeviation.

• SeeSpecialTestException 3.10.2COOKNUCLEARPLANT-<UNIT23/42-1AMENDMENT NO.

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POWERDISTRIBUTION LIMITSSURVEILLANCE REUIREMENTS (Continued) 4.2.1.2Theindicated AFDshallbeconsidered outsideofitstargetbandwhenatleast2of4or2of3OPERABLEexcorechannelsareindicating theAFDtobeoutsidethetargetband.Penaltydeviation outsideofthetargetbandshallbeaccumulated onatimebasisof:a.Apenaltydeviation ofoneminuteforeachoneminuteofPOWEROPERATION outsideofthetargetbandatTHERMALPOWERlevelsequaltoorabove50%ofRATEDTHERMALPOWER,andb.Apenaltydeviation ofonehalfminuteforeachoneminuteofPOWEROPERATION outsideofthetargetbandatTHERMALPOWERlevelsbetween15%and50%ofRATEDTHERMALPOWER.4.2.1.3Thetargetaxialfluxdifference fortheOPERABLEexcorechannelsshallbedetermined inconjunction withthemeasurement ofAPLasdefinedinSpecification 4.2.6.2.Theprovisions ofSpecification 4,0.4arenotapplicable.

4.2.1.4Theaxialfluxdifference targetbandaboutthetargetaxialfluxdifference shallbedetermined inconjunction withthemeasurement ofAPLasdefinedinSpecification 4'.6.2.Theallowable valuesofthetargetbandarespecified intheCOLR.Theprovisions ofSpecification 4.0.4arenotapplicable.

COOKNUCLEARPLANT-UNIT23/42-3AMENDMENT NO~

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~~~iThispageintentionally leftblank.COOKNUCLEARPLANT-UNIT23/42-4AMENDMENT NO.

POWERDISTRIBUTION LIMITSHEATFLUXHOTCHANNELFACTOR-FZLIMITINGCONDITION FOROPERATION 3.2.2F(Z)shallbelimitedbythefollowing relationships:

F(Z)<CFq/P[K(Z)]P>0.5Fq(Z)<CFQ/0.5[K(Z)]P<0.5'oCFQistheFlimitatRATEDTHERMALPOWERspecified intheCOLRoPTHERMALPOWERRATEDTHERMALPOWERoF(Z)isthemeasuredhotchannelfactorincluding a3%manufacturing t8lerance uncertainty anda5%measurement uncertainty.

oK(Z)isthenormalized F(Z)asafunctionofcoreheightspecified intheCOLR.APPLICABILITY:

MODE1ACTION:WithF(Z)exceeding itslimit:a~b.ReduceTHERMALPOWERatleast1%foreach18F(Z)exceedsthelimitwithin15minutesandsimilarly reducethePowerRangeNeutronFlux-High TripSetpoints withinthenext4hours;POWEROPERATION mayproceedforuptoatotalof72hours;subsequent POWEROPERATION mayproceedprovidedtheOverpower ATTripSetpoints havebeenreducedatleast1%foreach1%F(Z)exceedsthelimit.Identifyandcorrectthecauseoftheoutoflimitcondition priortoincreasing THERMALPOWERabovethereducedlimitrequiredbya,above;THERMALPOWERmaythenbeincreased providedF(Z)isdemonstrated throughincoremappingtobewithinitslimit.COOKNUCLEARPLANT-UNIT23/42-5AMENDMENT NO.

l0 Thispageintentionally leftblank.,COOKNUCLEARPLANT-UNIT23/42-8AMENDMENT NO.

(~~~gThispageintentionally leftblank.COOKNUCLEARPLANT-UNIT23/42-8(a)AMENDMENT NO.

Thispageintentionally leftblank.COOKNUCLEARPLANT-UNIT23/42-8(b)AMENDMENT NO.

~~-'ihlgI1'f POWERDISTRIBUTION LIMITSNUCLEARENTHALPYHOTCHANNELFACTOR-F~LIMITINGCONDITION FOROPERATION 3.2.3FpHshallbelimitedbythefollowing relationships:

F~<CFDH[1+PFDH(1-P)Jwhere:PisthefractionofRATEDTHERMALPOWERCFDHistheF>HlimitatRATEDTHERMALPOWERsPecified intheCOLRPFDHisthepowerfactormultiplier forFHspecified intheCOLRgHAPPLICABILITY:

MODE1ACTION:WithFHexceeding itslimit:~Ha.ReduceTHERMALPOWERtolessthan50%ofRATEDTHERMALPOWERwithin2hoursandreducethePowerRangeNeutronFlux-High TripSetpoints tolessthanorequalto55%ofRATEDTHERMALPOWERwithinthenext4hours.Demonstrate throughin-coremappingthatP<Hiswithinitslimitwithin24hoursafterexceeding thelimitorreduceTHERMALPOWERtolessthan5%ofRATEDTHERMALPOWERwithinthenext2hours,andIIdentifyandcorrectthecauseoftheout-of-limit condition priortoincreasing TH~POWER;subsequent POWEROPERATION mayproceed,providedthatF"Hisdemonstrated throughin-coremappingtobewithinitslimitatakominal508ofRATEDTHERMALPQWERpriortoexceeding thisTHERMALPOWER,atanominal75%ofRATED'THERMALPOWERpriortoexceeding thisTHERMALPOWERandwithin24hoursafterattaining 95%orgreaterRATEDTHERMALPOWER.COOKNUCLEARPLANT-UNIT23/42-9AMENDMENT NO.

POWERDISTRIBUTION LIMITSALLOWABLE POWERLEVEL-APLLIMITINGCONDITION FOROPERATION 3.2.6THERMALPOWERshallbelessthanorequaltoALLOWABLE POWERLEVEL(APL),givenbythefollowing relationships:

APL-minoverZofF(Z)xV(Z)xF oCFQistheFlimitatRATEDTHERMALPOWERspecified intheCOLRforWestingh9use orExxonfuel.oF(Z)isthemeasuredhotchannelfactor,including a3%m3nufacturing tolerance uncertainty anda5%measurement uncertainty.

oV(Z)isthefunctionspecified intheCOLR.oF,1~00exceptwhensuccessive steady-state powerdistribution mRpsindicateanincreaseinpeakpinpower,Fwithexposure.

Theneitherofthefollowing penalties, F,shallbetaken:PF-1.02or,PF-1.00providedthatSurveillance Requirement 4.2.6.2issRtisfied onceper7Effective FullPowerDaysuntil2successive mapsindicatethatthemaxoverZofF~isnotincreasing.

oTheabovelimitisnotapplicable inthefollowing coreregions.1)Lowercoreregion0%to10%inclusive.

2)Uppercore'region90%to100%inclusive.

APPLICABILITY'ODE 1COOKNUCLEARPLANT-UNIT23/42-19AMENDMENT NO.

34.2POWERDISTRIBUTION LIMITSBASESThespecifications ofthissectionprovideassurance offuelintegrity duringCondition I(NormalOperation) andII(Incidents ofModerateFrequency) eventsby:(a)'maintaining thecalculated DNBRinthecoreatorabovedesign=duringnormaloperation andinshorttermtransients, and(b)limitingthefissiongasrelease,fuelpellettemperature andcladdingmechanical properties towithinassumeddesigncriteria.

Inaddition, limitingthepeaklinearpowerdensityduringCondition Ieventsprovidesassurance thattheinitialconditions assumedfortheLOCAanalysesaremetandtheECCSacceptance criterialimitof2200Fisnotexceeded.

Thedefinitions ofcertainhotchannelandpeakingfactorsasusedinthesespecifications areasfollows:F(Z)HeatFluxHotChannelFactor,isdefinedasthemaximumlocalheatfluxonthesurfaceofafuelrodatcoreelevation Zdividedbytheaveragefuelrodheatflux,allowingforman-ufacturing tolerances onfuelpelletsandrods.NuclearEnthalpyRiseHotChannelFactor,isdefinedastheratiooftheintegraloflinearpoweralongtherodwiththehighestintegrated powertotheaveragerodpower.ThelimitsonF(Z)andFHarespecified intheCOLR.34.2.1AXIALFLUXDIFFERENCE AFDThelimitsonAXIALFLUXDIFFERENCE assurethattheF(Z)upperboundenvelopeisnotexceededduringeithernormaloperation oPintheeventofxenonredistribution following powerchanges.TheF(Z)upperboundenvelopeisspecified intheCOLR.Targetfluxdifference isdetermined atequilibrium xenonconditi.ons.

Thefulllengthrodsmaybepositioned withinthecoreinaccordance withtheirrespective, insertion limitsandshouldbeinsertedneartheirnormalpositionforsteadystateoperation athighpowerlevels.ThevalueoftheCOOKNUCLEARPLANT-UNIT2B3/42-1AMENDMENT NO.

~~fP~l'p~1'ItgIIfdW'I' POWERDISTRIBUTION LIMITSBASEStargetfluxdifference obtainedundertheseconditions dividedbythefractionofRATEDTHERMALPOWERisthetargetfluxdifference atRATEDTHERMALPOWERfortheassociated coreburnupconditions, Targetfluxdifferences forotherTHERMALPOWERlevelsareobtainedbymultiplying theRATEDTHERMALPOWERvaluebytheappropriate fractional THERMALPOWERlevel.Theperiodicupdatingofthetargetfluxdifference valueisnecessary toreflectcoreburnupconsiderations.

'AlthoughitisintendedthattheplantwillbeoperatedwiththeAXIALFLUXDIFFERENCE withinthetargetbandaboutthetargetfluxdifference, duringrapidplantTHERMALPOWERreductions, controlrodmotionwillcausetheAFDtodeviateoutsideofthetargetbandatreducedTHERMALPOWERlevels.Thisdeviation willnotaffectthexenonredistribution sufficiently tochangetheenvelopeofpeakingfactorswhichmaybereachedonasubsequent returntoRATEDTHERMALPOWER(with.theAFDwithinthetargetband)providedthetimedurationofthedeviation islimited.Accordingly, a1hourpenaltydeviation limitcumulative duringtheprevious24hoursisprovidedforoperation outsideofthetargetbandbutwithinthelimitsspecified intheCOLRwhileatTHERMALPOWERlevelsabove50$ofRATEDTHERMALPOWER.ForTHERMALPOWERlevelsbetween15%and50$ofRATEDTHERMALPOWER,deviations theAFDoutsideofthetargetbandarelesssignificant.

Thepenaltyof2hoursactualtimereflectsthisreducedsignificance.

Provisions formonitoring theAFDonanautomatic basisarederivedfromtheplantprocesscomputerthroughtheAFDMonitorAlarm.Thecomputerdetermines theoneminuteaverageofeachoftheOPERABLEexcoredetectoroutputsandprovidesanalarmmessageiftheAFDforatleast2of4or2,of3OPERABLEexcorechannelsareoutsidethetargetbandandtheTHERMALPOWERisgreaterthan90%or0.9xAPLofRATEDTHERMALPOWER(whichever isless).Duringoperation atTHERMALPOWERlevelsbetween50%and90%or0.9xAPLofRATEDTHERMALPOWER(whichever isless)andbetween158and50%RATEDTHERMALPOWER,thecomputeroutputsanalarmmessagewhenthepenaltydeviation accumulates beyondthelimitsof1hourand2hours,respectively.

Thebasisandmethodology forestablishing theselimitsispresented intopicalreportWCAP-8385, "PowerDistribution ControlandLoadFollowing Procedures."

COOKNUCLEARPLANT-UNIT2B3/42-2AMENDMENT NO.

~YiI~Thispageintentionally leftblank.COOKNUCLEARPLANT-UNIT2B3/42-3AMENDMENT NO.

I8*P,+lgf.I.~~1 POWERDISTRIBUTION LIMITSBASES34.2.2and34.2.3HEATFLUXHOTCHANNELFACTORANDNUCLEARENTHALPYRISEHOTCHANNELFACTORThelimitsonheatfluxhotchannelfactor,andnuclearenthalpyrisehotchannelfactorensurethat1)thedesignlimitsonpeaklocalpowerdensityandminimumDNBRarenotexceededand2)intheeventofaLOCAthepeakfuelcladtemperature willnotexceedthe2200FECCSacceptance 0criterialimit.Eachoftheseismeasurable butwillnormallyonlybedetermined periodically asspecified inSpecifications 4.2.2.1,4.2.2.2,4.2.3,4.2.6.1and4.2.6.2.Thisperiodicsurveillance 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.Theaxialpowerdistribution, expressed intermsofAXIALFLUXDIFFERENCE, ismaintained withinthelimits.Fwillbemaintained withinitslimitsasspecified intheCOLRpovide%conditions a.throughd.abovearemaintained.

Therelaxation of~asafunctionofTHERMAL'POWERallowschangesintheradialpowershapeforallpermissible rodinsertion limits.Theformofthisrelaxation for-DNBRlimitsisdiscussed inSection2.1.1ofthisbasis.WhenanFmeasurement istaken,bothexperimental errorandmanu-facturing tolerance mustbeallowedfor.5%istheappropriate allowance forafullcoremaptakenwiththeincoredetectorfluxmappingsystemand3Sintheappropriate allowance formanufacturing tolerance.

COOKNUCLEARPLANT-UNIT2B3/42-4AMENDMENT NO.

ADMINISTRATIVE CONTROLSMONTHLYREACTOROPERATING REPORTCOREOPERATING LIMITSREPORT6.9.1.11.1 Coreoperating limitsshallbeestablished anddocumented intheCOREOPERATING LIMITSREPORTbeforeeachreloadcycleoranyremaining partofareloadcycleforthefollowing:

a.Moderator Temperature Coefficient LimitsforSpecification 3/4.1.1.4, b.RodDropTimeLimitsforSpecification 3/4.1.3.4, c.ShutdownRodInsertion LimitsforSpecification 3/4.1.3.5, d.ControlRodInsertion LimitsforSpecification 3/4.1.3.6, e.AxialFluxDifference forSpecification 3/4.2.1,,

f.He'atFluxHotChannelFactorforSpecification 3/4.2.2,g.NuclearEnthalpyRiseHotChannelFactorforSpecification 3/4.2.3,andh.Allowable PowerLevelforSpecification 3/4.2.6.6.9.1.11.2 Theanalytical methodsusedtodetermine, thecoreoperating limitsshallbethosepreviously reviewedandapprovedbytheNRCin:a.WCAP-9272-P-A, "Westinghouse ReloadSafetyEvaluation Methodology,"

July1985(Westinghouse Proprietary),

b.WCAP-8385, "PowerDistribution ControlandLoadFollowing Procedures

-TopicalReport,"September 1974(Westinghouse Proprietary),

C.WCAP-10216-P-A, PartB,"Relaxation ofConstantAxialOffsetControl/F Surveillance Technical Specification,"

June1983(Westingh9use Proprietary),

COOKNUCLEARPLANT-UNIT26-19AMENDMENT NO.

I~pl'l'1 Itv~~IIjADMINISTRATIVE CONTROLSCOREOPERATING LIMITSREPORT(Continued) e.'CAP-10266-P-A Rev.2,"The1981VersionofWestinghouse Evaluation ModeUsingBASHCode,"March1987(Westinghouse Proprietary).

6.9.1.11.3 Thecoreoperating limitsshallbedetermined sothatallapplicable limits(e.g.,fuelthermal-mechanical limits,corethermal-hydraulic limits,ECCSlimits,nuclearlimitssuchasshutdownmargin,andtransient andaccidentanalysislimits)ofthesafetyanalysisaremet.6.9.1.11.4 TheCOREOPERATING LIMITSREPORT,including anymid-cycle revisions orsupplements thereto,shallbeprovideduponissuance, foreachreloadcycle,totheNRCdocumentcontroldeskwithcopiestotheRegionalAdministrator andResidentInspector.

SPECIALREPORTS6.9.2Specialreportsshallbesubmitted totheRegionalAdministrator withinthetimeperiodspecified foreachreport.Thesereportsshallbesubmitted coveringtheactivities identified belowpursuanttotherequirements oftheapplicable reference specification:

a.b.ECCSActuation, Specifications 3.5.2and3.5.3.hInoperable SeismicMonitoring Instrumentation, UnitNo.1,Specification 3.3.3.3."c.Inoperable Meteorological Monitoring Instrumentation, UnitNo.1,Specification 3.3.3.4.d.FireDetection Instrumentation, Specification 3.3'.8.e.FireSuppression Systems,Specifications 3.7.9.1,3.7.9.2,3.7.9.3and3.7.9.4.f.SeismicEventAnalysis, Specification 4.3.3.3.2.

g.SealedSourceleakageinexcessoflimits,Specification 4.7.8.1.3.

h.Moderator Temperature Coefficient, Specification 3.1.1.4.COOKNUCLEARPLANT-UNIT26-19aAMENDMENT NO.

I)~~4IAttachment 3TOAEP:NRC:1077A SAMPLECOREOPERATING LIMITSREPORT DONALDC.COOKNUCLEARPLANTUNIT2CYCLE7,SAMPLECOREOPERATING LIMITSREPORTRevision0February5,1990 SAMPLECOLRforDONALDC.COOKNUCLEARPLANTUNIT2CYCLE71.0COREOPERATING LIMITSREPORTThisisasampleCoreOperating LimitsReportforDonaldC.CookNuclearPlantUnit2Cycle7and,therefore, hasnotbeenpreparedinaccordance withtherequirements ofTechnical Specification 6.9.1.11.

TheTechnical Specifications affectedbythisreportarelistedbelow:3/4.1.1.4 3/4.1~3.13/4.1.3.4 3/4.1.3.5 3/4'.3.63/4.2.13/4.2.23/4.2.33/4.2.6Moderator Temperature Coefficient MovableControlAssemblies GroupHeightRodDropTimeShutdownRodInsertion LimitsControlRodsLimitsAxialFluxDifference HeatFluxHotChannelFactorNuclearEnthalpyRiseHotChannelFactorAllowable PowerLevelPage1of11 SAMPLECOLRforDonaldC.CookNuclearPlantUnit2Cycle72'OPERATING LIMITSThecyle-specific parameter limitsforthespecifications listedinSection1.0arepresented inthefollowing subsections.

Theselimitshavebeendeveloped usingtheNRC-approved methodologies specified inTechnical Specification 6.9.1.11.

2.1Moderator TemeratureCoefficient (Specification 3/4.1.1.4) 2.1.1TheModerator Temperature Coefficient EOLLimitis:TheEOL/ARO/RTP-MTC shallbelessnegativethanthevaluegiveninFigurel.where:AROstandsforAllRodsOutEOLstandsforEndofCycleLifeRTPstandsforRatedThermalPowerHZPstandsforHotZeroThermalPower2.1.2TheMTCSurveillance limitis:The300ppm/ARO/RTP-MTC shouldbelessnegativethanorequalto-2.9E-4Ak/k/'F.Page2ofll

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SAMPLECOLRforDonaldC.CookNuclearPlantUnit2Cycle72.2RodDroTime,DroHeiht(Specification 3/4.1.3.4) 2.2.1Allrodsshallbedroppedfromatleast228steps.2.3ShutdownRodInsertion Limit(Specification 3/4.1.3.5) 2.3.1Theshutdownrodsshallbewithdrawn toatleast228steps.2.4ControlRodInsertion Limits(Specification 3/4.1.3.6, and3/4.1.3.1) 2.4.1Thecontrolbanksshallbelimitedinphysicalinsertion asshowninFigure2.2.4.2Successive ControlBanksshalloverlapby100steps.ThesequenceforControlBankwithdrawal shallbeControlBankA,ControlBankB,ControlBankC,andControlBankD.2.5AxialFluxDifference (Specification 3/4.2.1)2.5.1TheAllowable Operation LimitsareprovidedinFigure3.2.5.2TheAXIALFLUXDIFFERENCE (AFD)targetbandduringbaseloadoperations is+3%,-3%forcoreaverageburnup(0.0MWD/MTU.2.5.3TheAFDtargetbandis+5%,-5%forcoreaverageaccumulated burnup>0.0MWD/MTUPage3of11 h+~~~SAMPLECOLRforDonaldC.CookNuclearPlantUnit2Cycle72.5HeatFluxHotChannelFactor-F(Z)(Specification 3.2.2)CFQF(Z)<---*K(Z)QforP>0.5F(Z)<2*CFQ*K(Z)forP<0.5THERMALPOWERwhere'RATEDTHERMALPOWER2.5.1CFQ-2.10forANFfuel1.97forWestinghouse fuel2.5.2K(Z)isprovidedinFigures4and5fortherespective fueltype2.5.3V(Z)isprovidedinFigure6Page4of11

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SAMPLECOLRforDonaldC.CookNuclearPlantUnit2Cycle72.6NuclearEnthalRiseHotChannelFactor-F(Specification 3/4.2.3)F<CFDH*(1+PFDH*(1-P))THERMALPOWERwhere:PRATEDTHERMALPOWER2.6.1CFDH-1.49forANFfuel-1.48forWestinghouse fuel2.6.2PFDH-0.2forANFfuel-0.2forWestinghouse fuelPage5of11 FIGURE1MODERATOR TEMPERATURE COEFFICIENT (MTC)VS.VESSELAVERAGEMODERATOR TEMPERATURE MTC(PCM/DEGF)-25.0-30.0-35.0MO.OM5.0545555565575VESSELAVERAGEMODERATOR TEMPERATURE (DEGF) p'figure2~IyWithdrawn)

(007228)(0.62,228)(0,212)BANKB~(1.0.189)'t5084s4)Cz100I(084SANKCBANK0:504(FullyIncited)(0.19,0)020.40.60$FRACTIONOFRATEDTHERMALPOSER1.0Figure3.1~1RODBANKINSERTION I-IMITSVERSUSTHERMALPOSERFOURLOOPOPERATION 0.C.COOK-UNIT23/41-26Page7of11 y,~~.~~CI-I'I1re FIGURE3.2-1'LLO'I/ABLE.

DEVIATION FROMTARGETFLUXDIFFERENCE 1120if100~80~SO-.(-.5,50}Unocjcepto Operhtion

}+37~}Torge(-10,0)25.5Il)AccCptobl 0peI{-aI00).{+090)+57'ionI(+2>.S)IIIIIij}(i+10.90) u'occeOperotitoblelnorge!t!nd)20OW00-20->0010f)evle<ionfroeTe<RetFluaOlfference

~~>0l FIGURE4K(Z)-NORMALIZED FQ(Z)ASAFUNCTIONOFCOREHEIGHTWESTINGHOUSE FUEL(6.0,1.0)(11.37,0.93)0.,0.(12.0,0.754)0.0.io12.COREHEIGHT(FT) a'r~~

FIGURE5K(Z)-NORMALIZED FQ(Z)ASAFUNCTIONOFCOREH'EIGHTEXXONNUCLEARCO.FUELK(Z)(6.0,'1.0)(11.14,0.93)0.0.{12.0,0.710)0.0.010COREHEIGHT{FT) a.<geoClt0 v(z)2.001.181.161.14FIGURE6V(Z)ASAFUNCTIONOFCOREHEIGHT(11.25,1.15)1.12-1.101.081.061.041.021.000+5%TARGETBAND23%TARGETBAND(9.25,1.11)(9.25,1.08)10(11.5,1.12)COREHEIGHT r.ilpgaI