ML17328A563

From kanterella
Revision as of 13:52, 4 June 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Proposed Tech Specs Re Implementation of Core Operating Limits Rept,Per Generic Ltr 88-16
ML17328A563
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 02/06/1990
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17328A562 List:
References
GL-88-16, NUDOCS 9002140165
Download: ML17328A563 (60)


Text

Attachment2TOAEP;NRC:1077APROPOSEDTECHNICALSPECIFICATIONCHANGESnvocv~pp~p+pzPK05ppppPgg INDEXDEFINITIONSSECTIONPAGE1.0DEFINITIONSSolidificationOffsiteDoseCalculationManual(ODCM)GaseousRadwasteTreatmentSystemVentilationExhaustTreatmentSystemPurge-PurgingVentingMember(s)OfThePublicSiteBoundaryUnrestrictedAreaAllowablePowerLevelCoreOperatingLimitsReport(COLR)OperationalModes(Table1.1)FrequencyNotation(Table1.2)1-71-71-71-7'-71-71-81-81-81-81-81-91-10COOKNUCLEARPLANT-UNIT2AMENDMENTNO~

~~

DEFINITIONS.MEMBERSOFTHEPUBLIC1.35MEMBER(S)OFTHEPUBLICshallincludeallpersonswhoarenotoccupationallyassociatedwiththePlant.Thiscategorydoesnotincludeemployeesoftheutility,itscontractorsoritsvendors.Alsoexcludedfromthiscategoryarepersonswhoenterthesitetoserviceequipmentortomakedeliveries.Thiscategorydoesincludepersonswhouseportionsofthesiteforrecreational,occupationalorotherpurposesnotassociatedwiththePlant.SITEBOUNDARY1.36TheSITEBOUNDARYshallbethatlinebeyondwhichthelandisnotowned,leasedorotherwisecontrolledbythelicensee.UNRESTRICTEDAREA1.37AnUNRESTRICTEDAREAshallbeanyareaatorbeyondtheSITEBOUNDARYtowhichaccessisnotcontrolledbythelicenseeforpurposesofprotectionofindividualsfromexposuretoradiationandradioactivematerialsoranyareawithinthesiteboundaryusedforresidentialquartersorindustrial,commercial,institutionaland/orrecreationalpurposes.ALLOWABLE'OWERLEVELAPL1.38APLmeans"allowablepowerlevel"'hichisthatpowerlevel,lessthanorequalto100%RATEDTHERMALPOWER,atwhichtheplantmaybeoperatedtoensurethatpowerdistributionlimitsaresatisfied.COREOPERATINGLIMITSREPORTCOLR1.39TheCOLRistheunit-specificdocumentthatprovidescoreoperatinglimitsforthecurrentoperatingreloadcycle.Thesecycle-specifccoreoperatinglimitsshallbedeterminedforeachreloadcycleinaccordancewithSpecification6.9.1.11.Unitoperationwithintheseoperatinglimitsisaddressedinindividualspecifications.COOKNUCLEARPLANT-UNIT21-8AMENDMENTNO.

~~

SAFETYLIMITSBASESThecurvesarebasedonanuclearenthalpyrisehotchannelfactor,definedintheCOLRandareferencecosinewithapeakof1.55foraxialpowershape.AnallowanceisincludedforanincreaseinF"atreducedpowerbasedontheexpression:F~-CFDH[1+PFDH(1-P)]where:CFDHistheFHlimitatRTPspecifiedintheCOLRAHPFDHisthepowerfactormultiplierforF~providedintheCOLRPisthefractionofRATEDTHERMALPOWERTheselimitingheatfluxconditionsarehigherthanthosecalculatedfortherangeofallcontrolrodsfullywithdrawntothemaximumallowablecontrolrodinsertionassumingtheaxialpowerimbalanceiswithinthelimitsofthefl(AI)functionoftheOvertemperaturetrip.Whentheaxialpowerimbalanceisnotwithinthetolerance,theaxialpowerimbalanceeffectontheOvertemperatureATtripswillreducethesetpointstoprovideprotectionconsistentwithcoresafetylimits.2.1.2REACTORCOOLANTSYSTEMPRESSURETherestrictionofthisSafetyLimitprotectstheintegrityoftheReactorCoolantSystemfromoverpressurizationandtherebypreventsthereleaseofradionuclidescontainedinthereactorcoolantfromreachingthecontainmentatmosphere.iThereactorpressurevesselandpressurizeraredesignedtoSectionIIIoftheASMECodeforNuclearPowerPlantwhichpermitsamaximumtransientpressureof110%(2735psig)ofdesignpressure.TheReactorCoolantSystempiping,valvesandfittings,aredesignedtoANSIB31.11967Edition,whichpermitsamaximumtransientpressureof1208(2985psig)ofcomponentdesignpressure.TheSafetyLimitof2735psigisthereforeconsistentwiththedesigncriteriaandassociatedcoderequirements.TheentireReactorCoolantSystemishydrotestedat3107psig,125%ofdesignpressure,todemonstrateintegritypriortoinitialoperation.COOKNUCLEARPLANT-UNIT2B2-2AMENDMENTNO.

1~Ar.V>1t REACTIVITYCONTROLSYSTEMSMODERATORTEMPERATURECOEFFICIENTLIMITINGCONDITIONFOROPERATION3.1.1.4Themoderatortemperaturecoefficient(MTC)shallbewithinthelimitsspecifiedintheCOLR.ThemaximumupperlimitshallbelessthanorequaltothelimitshowninFigure3.1-2.APPLICABILITY:-BOLLimit-MODES1and2*only¹'OLLimit-MODES1,2and3only¹ACTION:a~WiththeMTCmorepositive,thantheBOLlimitspecifiedintheCOLR:l.EstablishandmaintaincontrolrodwithdrawallimitssufficienttorestoretheMTCtowithinitslimitwithin24hoursorbeinHOTSTANDBYwithinthenext6hours.ThesewithdrawallimitsshallbeinadditiontotheinsertionlimitsofSpecification3.1.3.6.2.MaintainthecontrolrodswithinthewithdrawallimitsestablishedaboveuntilsubsequentmeasurementverifiesthattheMTChasbeenrestoredtowithinitslimitfortheallrodswithdrawncondition.PrepareandsubmitaSpecialReporttotheCommissionpursuanttoSpecification6.9.2within10daysdescribingthevalueofthemeasuredMTC,theinterimcontrolrodwithdrawallimitsandthepredictedaveragecoreburnupnecessaryforrestoringthepositiveMTCtowithinitslimitfortheallrodswithdrawncondition.WiththeMTCmorenegativethantheEOLlimitspecifiedintheCOLR,beinHOTSHUTDOWNwithin12hours.*WithKfgreaterthanorequalto1.0¹SeeSpecialTestException3.10.3effCOOKNUCLEARPLANT-UNIT2AMENDMENTNO.

1Iit4 REACTIVITYCONTROLSYSTEMSSURVEILLANCEREUIREMENTS4.1.1.4.1TheMTCshallbedeterminedtobewithinitslimitsbyconfirmatorymeasurements.MeasuredMTCvaluesshallbeextrapolatedand/orcompensatedtopermitdirectcomparisonwiththeabovelimits.4.1.1.4.2TheMTCshallbedeterminedtobewithinitslimitsduringeachfuelcycleasfollows:a)TheMTCshallbemeasuredandcomparedtotheBOLlimitspecifiedintheCOLRpriortoinitialoperationabove5%ofRATEDTHERMALPOWER,aftereachfuelloading.b)TheMTCshallbemeasuredatanyTHERMALPOWERwithin7EFPDafterreachinganequilibriumboronconcentrationof300ppm.Themeasuredvalueshallbecomparedtothe300ppmsurveillancelimitspecified'intheCOLR.IntheeventthiscomparisonindicatesthattheMTCwillbemorenegativethantheEOLlimit,theMTCshallberemeasuredatleastonceper14EFPDduringtheremainderofthefuelcycleandtheMTCvaluecomparedtotheEOLlimit.COOKNUCLEARPLANT-UNIT23/41-6AMENDMENTNO~

~pREACTIVITYCONTROLSYSTEMSLIMITINGCONDITIONFOROPERATIONContinuedc)Apowerdistributionmapj,sobtainedfromthemovableincoredetectorsandF(Z)andF<areverifiedtobewithintheirlimitswithin79hours,'n5d)e)EithertheTHERMALPOWERlevelisreducedtolessthanorequalto75%ofRATEDTHERMALPOWERwithinonehourandwithinthenext4hoursthehighneutronfluxtripsetpointisreducedtolessthanorequalto85$ofRATEDTHERMALPOWER,orITheremainderoftherodsinthegroupwiththeinoperablerodarealignedtowithin+12stepsoftheinoperablerodwithinonehourwhilemaintainingtherodsequenceandinsertionlimitsasspecifiedintheCOLR;theTHERMALPOWERlevelshallberestrictedpursuanttoSpecification3.1.3.6duringsubsequentoperation.SURVEILLANCEREUIREMENTSj4.1.3.1.1'Thepositionofeachfulllengthrodshallbedeterminedtobewithinthegroupdemandlimitbyverifyingtheindividualrodpositionsatleastonceper12hoursexceptduringtimeintervalswhentheRodPositionDeviationMonitorisinoperable,thenverifythegrouppositionsatleastonceper4hours.4.1.3.1.2EachfulllengthrodnotfullyinsertedinthecoreshallbedeterminedtobeOPERABLEbymovementofat'east8stepsinanyonedirectionatleastonceper31days.COOKNUCLEARPLANT-UNIT23/41-19AMENDMENTNO.

~~

REACTIVITYCONTROLSYSTEMSRODDROPTIMELIMITINGCONDITIONFOROPERATION3.1.3.4Theindividualfulllength(shutdownandcontrol)roddroptimefromthefullywithdrawnposition(specifiedintheCOLR)shallbelessthanIorequalto2.2secondsfrombeginningofdecayofstationarygrippercoilvoltagetodashpotentrywith:a.Tgreaterthanorequalto541F,and0avgb.Allreactorcoolantpumpsoperating.APPLICABILITY:MODES1AND2ACTION:Withthedroptimeofanyfulllengthroddeterminedtoexceedtheabovelimit,restoretheroddroptimetowithintheabovelimitpriortoproceedingtoMODE1or2.SURVEILLANCEREUIREMENTS4.1.3.4Theroddroptimeoffulllengthrodsshallbedemonstratedthroughmeasurementpriortoentering,MODE2:a.Forallrodsfollowingeachremovalofthereactorvesselhead,b.Forspecificallyaffectedindividualrodsfollowinganymaintenanceonormodificationtothecontrolroddrivesystemwhichcouldaffectthedroptimeofthosespecificrods,andc.Atleastonceper18months.COOKNUCLEARPLANT-UNIT23/41-23AMENDMENTNO.

REACTIVITYCONTROLSYSTEMSSHUTDOWNRODINSERTIONLIMITLIMITINGCONDITIONFOROPERATION3.1.3.5AllshutdownrodsshallbelimitedinphysicalinsertionasspecifiedintheCOLR.APPLICABILITY:MODES1*and2*¹ACTION:WithamaximumofoneshutdownrodinsertedbeyondtheinsertionlimitspecifiedintheCOLR,exceptforsurveillancetestingpursuanttoSpecification4.1.3.1.2,withinonehoureither:a.RestoretherodtowithintheinsertionlimitspecifiedintheCOLR,orb.DeclaretherodtobeinoperableandapplySpecification3.1.3.1.SURVEILLANCEREUIREMENTS4.1.3.5EachshutdownrodshallbedeterminedtobewithintheinsertionlimitspecifiedintheCOLR:a.Within15minutespriortowithdrawalofanyrodsincontrolbanksA,B,CorDduringanapproachtoreactorcriticality,andb.Atleastonce.per12hoursthereafter.*SeeSpecialTestExceptions3.10.2and3.10.3.¹WithKffgreaterthanorequalto1.0effCOOKNUCLEARPLANT-UNIT23/41-24AMENDMENTNO.

~~REACTIVITYCONTROLSYSTEMSCONTROLRODINSERTIONLIMITSLIMITINGCONDITIONFOROPERATION3.1.3.6ThecontrolbanksshallbelimitedinphysicalinsertionasspecifiedintheCOLR.APPLICABILITY'ODES1*and2*¹.ACTION:Withthecontrolbanksinsertedbeyondtheinsertionlimits,exceptforsurveillancetestingpursuanttoSpecification4.1.3.1.2;either:a.Restorethecontrolbankstowithinthelimitswithintwohours,orb.ReduceTHERMALPOWERwithintwohourstolessthanorequaltothatfractionofRATEDTHERMALPOWERwhich,isallowedbythegrouppositionusingtheinsertionlimitsspecifiedintheCOLR,orc.BeinatleastHOTSTANDBYwithin6hours.SURVEILLANCEREUIREMENTS4.1.3.6Thepositionofeachcontrolbankshallbedeterminedtobewithintheinsertionlimitsatleastonceper12hoursexceptduringtimeintervalswhentheRodInsertionLimitMonitorisinoperable,thenverifytheindividualrodpositionsatleastonceper4hours.*SeeSpecialTestExceptions3.10.2and3.10.3¹WithKffgreaterthanorequalto1.0.effCOOKNUCLEARPLANT-UNIT23/41-25AMENDMENTNO.

~~Thispageintentionallyleftblank.COOKNUCLEARPLANT-UNIT23/41-26AMENDMENTNO.

'Pljl, 3.4.2POWERDISTRIBUTIONLIMITSAXIALFLUXDIFFERENCEAFDLIMITINGCONDITIONFOROPERATION3.2.1TheindicatedAXIALFLUXDIFFERENCE(AFD)shallbemaintainedwithinthetargetbandaboutatargetfluxdifference.ThetargetbanisspecifiedintheCOLR.APPLICABILITY:MODE1above50%RATEDTHERMALPOWER*ACTION:WiththeindicatedAXIALFLUXDIFFERENCEoutsideofthetargetbandaboutthetargetfluxdifferenceandwithTHERMALPOWER:1.Above90%or0.9xAPL(whicheverisless)ofRATEDTHERMALPOWER,within15minutes:a)EitherrestoretheindicatedAFDtowithinthetargetbandlimits,orb)ReduceTHERMALPOWERtolessthan90%or0.9xAPL(whi'cheverisless)ofRATEDTHERMALPOWER.2.Between50%and90%or0.9xAPL(whicheverisless)ofRATEDTHERMALPOWER')POWEROPERATIONmaycontinueprovided:1)TheindicatedAFDhasnotbeenoutsideofthetargetbandformorethan1hourpenaltydeviationcumulativeduringtheprevious24hours,and2)TheindicatedAFDiswithinthelimitsspecifiedintheCOLR.Otherwise,reduceTHERMALPOWERtolessthan50%ofRATEDTHERMALPOWERwithin30minutesandreducethePowerRangeNeutronFlux-HighTripSetpointstolessthanorequalto55%ofRATEDTHERMALPOWERwithinthenext4hours.b)SurveillancetestingofthePowerRangeNeutronFluxChannelsmaybeperformedpursuanttoSpecification4.3.1.1.1providedtheindicatedAFDismaintainedwithinthelimitspecifiedintheCOLR.Atotalof16hoursoperationmaybeaccumulatedwiththeAFDoutsideofthetargetbandduringthistestingwithoutpenaltydeviation.*SeeSpecialTestException3.10.2COOKNUCLEARPLANT-<UNIT23/42-1AMENDMENTNO.

~~

POWERDISTRIBUTIONLIMITSSURVEILLANCEREUIREMENTS(Continued)4.2.1.2TheindicatedAFDshallbeconsideredoutsideofitstargetbandwhenatleast2of4or2of3OPERABLEexcorechannelsareindicatingtheAFDtobeoutsidethetargetband.Penaltydeviationoutsideofthetargetbandshallbeaccumulatedonatimebasisof:a.ApenaltydeviationofoneminuteforeachoneminuteofPOWEROPERATIONoutsideofthetargetbandatTHERMALPOWERlevelsequaltoorabove50%ofRATEDTHERMALPOWER,andb.ApenaltydeviationofonehalfminuteforeachoneminuteofPOWEROPERATIONoutsideofthetargetbandatTHERMALPOWERlevelsbetween15%and50%ofRATEDTHERMALPOWER.4.2.1.3ThetargetaxialfluxdifferencefortheOPERABLEexcorechannelsshallbedeterminedinconjunctionwiththemeasurementofAPLasdefinedinSpecification4.2.6.2.TheprovisionsofSpecification4,0.4arenotapplicable.4.2.1.4TheaxialfluxdifferencetargetbandaboutthetargetaxialfluxdifferenceshallbedeterminedinconjunctionwiththemeasurementofAPLasdefinedinSpecification4'.6.2.TheallowablevaluesofthetargetbandarespecifiedintheCOLR.TheprovisionsofSpecification4.0.4arenotapplicable.COOKNUCLEARPLANT-UNIT23/42-3AMENDMENTNO~

~~~~'

~~~iThispageintentionallyleftblank.COOKNUCLEARPLANT-UNIT23/42-4AMENDMENTNO.

POWERDISTRIBUTIONLIMITSHEATFLUXHOTCHANNELFACTOR-FZLIMITINGCONDITIONFOROPERATION3.2.2F(Z)shallbelimitedbythefollowingrelationships:F(Z)<CFq/P[K(Z)]P>0.5Fq(Z)<CFQ/0.5[K(Z)]P<0.5'oCFQistheFlimitatRATEDTHERMALPOWERspecifiedintheCOLRoPTHERMALPOWERRATEDTHERMALPOWERoF(Z)isthemeasuredhotchannelfactorincludinga3%manufacturingt8leranceuncertaintyanda5%measurementuncertainty.oK(Z)isthenormalizedF(Z)asafunctionofcoreheightspecifiedintheCOLR.APPLICABILITY:MODE1ACTION:WithF(Z)exceedingitslimit:a~b.ReduceTHERMALPOWERatleast1%foreach18F(Z)exceedsthelimitwithin15minutesandsimilarlyreducethePowerRangeNeutronFlux-HighTripSetpointswithinthenext4hours;POWEROPERATIONmayproceedforuptoatotalof72hours;subsequentPOWEROPERATIONmayproceedprovidedtheOverpowerATTripSetpointshavebeenreducedatleast1%foreach1%F(Z)exceedsthelimit.IdentifyandcorrectthecauseoftheoutoflimitconditionpriortoincreasingTHERMALPOWERabovethereducedlimitrequiredbya,above;THERMALPOWERmaythenbeincreasedprovidedF(Z)isdemonstratedthroughincoremappingtobewithinitslimit.COOKNUCLEARPLANT-UNIT23/42-5AMENDMENTNO.

l0 Thispageintentionallyleftblank.,COOKNUCLEARPLANT-UNIT23/42-8AMENDMENTNO.

(~~~gThispageintentionallyleftblank.COOKNUCLEARPLANT-UNIT23/42-8(a)AMENDMENTNO.

Thispageintentionallyleftblank.COOKNUCLEARPLANT-UNIT23/42-8(b)AMENDMENTNO.

~~-'ihlgI1'f POWERDISTRIBUTIONLIMITSNUCLEARENTHALPYHOTCHANNELFACTOR-F~LIMITINGCONDITIONFOROPERATION3.2.3FpHshallbelimitedbythefollowingrelationships:F~<CFDH[1+PFDH(1-P)Jwhere:PisthefractionofRATEDTHERMALPOWERCFDHistheF>HlimitatRATEDTHERMALPOWERsPecifiedintheCOLRPFDHisthepowerfactormultiplierforFHspecifiedintheCOLRgHAPPLICABILITY:MODE1ACTION:WithFHexceedingitslimit:~Ha.ReduceTHERMALPOWERtolessthan50%ofRATEDTHERMALPOWERwithin2hoursandreducethePowerRangeNeutronFlux-HighTripSetpointstolessthanorequalto55%ofRATEDTHERMALPOWERwithinthenext4hours.Demonstratethroughin-coremappingthatP<Hiswithinitslimitwithin24hoursafterexceedingthelimitorreduceTHERMALPOWERtolessthan5%ofRATEDTHERMALPOWERwithinthenext2hours,andIIdentifyandcorrectthecauseoftheout-of-limitconditionpriortoincreasingTH~POWER;subsequentPOWEROPERATIONmayproceed,providedthatF"Hisdemonstratedthroughin-coremappingtobewithinitslimitatakominal508ofRATEDTHERMALPQWERpriortoexceedingthisTHERMALPOWER,atanominal75%ofRATED'THERMALPOWERpriortoexceedingthisTHERMALPOWERandwithin24hoursafterattaining95%orgreaterRATEDTHERMALPOWER.COOKNUCLEARPLANT-UNIT23/42-9AMENDMENTNO.

POWERDISTRIBUTIONLIMITSALLOWABLEPOWERLEVEL-APLLIMITINGCONDITIONFOROPERATION3.2.6THERMALPOWERshallbelessthanorequaltoALLOWABLEPOWERLEVEL(APL),givenbythefollowingrelationships:APL-minoverZofF(Z)xV(Z)xFoCFQistheFlimitatRATEDTHERMALPOWERspecifiedintheCOLRforWestingh9useorExxonfuel.oF(Z)isthemeasuredhotchannelfactor,includinga3%m3nufacturingtoleranceuncertaintyanda5%measurementuncertainty.oV(Z)isthefunctionspecifiedintheCOLR.oF,1~00exceptwhensuccessivesteady-statepowerdistributionmRpsindicateanincreaseinpeakpinpower,Fwithexposure.Theneitherofthefollowingpenalties,F,shallbetaken:PF-1.02or,PF-1.00providedthatSurveillanceRequirement4.2.6.2issRtisfiedonceper7EffectiveFullPowerDaysuntil2successivemapsindicatethatthemaxoverZofF~isnotincreasing.oTheabovelimitisnotapplicableinthefollowingcoreregions.1)Lowercoreregion0%to10%inclusive.2)Uppercore'region90%to100%inclusive.APPLICABILITY'ODE1COOKNUCLEARPLANT-UNIT23/42-19AMENDMENTNO.

34.2POWERDISTRIBUTIONLIMITSBASESThespecificationsofthissectionprovideassuranceoffuelintegrityduringConditionI(NormalOperation)andII(IncidentsofModerateFrequency)eventsby:(a)'maintainingthecalculatedDNBRinthecoreatorabovedesign=duringnormaloperationandinshorttermtransients,and(b)limitingthefissiongasrelease,fuelpellettemperatureandcladdingmechanicalpropertiestowithinassumeddesigncriteria.Inaddition,limitingthepeaklinearpowerdensityduringConditionIeventsprovidesassurancethattheinitialconditionsassumedfortheLOCAanalysesaremetandtheECCSacceptancecriterialimitof2200Fisnotexceeded.Thedefinitionsofcertainhotchannelandpeakingfactorsasusedinthesespecificationsareasfollows:F(Z)HeatFluxHotChannelFactor,isdefinedasthemaximumlocalheatfluxonthesurfaceofafuelrodatcoreelevationZdividedbytheaveragefuelrodheatflux,allowingforman-ufacturingtolerancesonfuelpelletsandrods.NuclearEnthalpyRiseHotChannelFactor,isdefinedastheratiooftheintegraloflinearpoweralongtherodwiththehighestintegratedpowertotheaveragerodpower.ThelimitsonF(Z)andFHarespecifiedintheCOLR.34.2.1AXIALFLUXDIFFERENCEAFDThelimitsonAXIALFLUXDIFFERENCEassurethattheF(Z)upperboundenvelopeisnotexceededduringeithernormaloperationoPintheeventofxenonredistributionfollowingpowerchanges.TheF(Z)upperboundenvelopeisspecifiedintheCOLR.Targetfluxdifferenceisdeterminedatequilibriumxenonconditi.ons.Thefulllengthrodsmaybepositionedwithinthecoreinaccordancewiththeirrespective,insertionlimitsandshouldbeinsertedneartheirnormalpositionforsteadystateoperationathighpowerlevels.ThevalueoftheCOOKNUCLEARPLANT-UNIT2B3/42-1AMENDMENTNO.

~~fP~l'p~1'ItgIIfdW'I' POWERDISTRIBUTIONLIMITSBASEStargetfluxdifferenceobtainedundertheseconditionsdividedbythefractionofRATEDTHERMALPOWERisthetargetfluxdifferenceatRATEDTHERMALPOWERfortheassociatedcoreburnupconditions,TargetfluxdifferencesforotherTHERMALPOWERlevelsareobtainedbymultiplyingtheRATEDTHERMALPOWERvaluebytheappropriatefractionalTHERMALPOWERlevel.Theperiodicupdatingofthetargetfluxdifferencevalueisnecessarytoreflectcoreburnupconsiderations.'AlthoughitisintendedthattheplantwillbeoperatedwiththeAXIALFLUXDIFFERENCEwithinthetargetbandaboutthetargetfluxdifference,duringrapidplantTHERMALPOWERreductions,controlrodmotionwillcausetheAFDtodeviateoutsideofthetargetbandatreducedTHERMALPOWERlevels.ThisdeviationwillnotaffectthexenonredistributionsufficientlytochangetheenvelopeofpeakingfactorswhichmaybereachedonasubsequentreturntoRATEDTHERMALPOWER(with.theAFDwithinthetargetband)providedthetimedurationofthedeviationislimited.Accordingly,a1hourpenaltydeviationlimitcumulativeduringtheprevious24hoursisprovidedforoperationoutsideofthetargetbandbutwithinthelimitsspecifiedintheCOLRwhileatTHERMALPOWERlevelsabove50$ofRATEDTHERMALPOWER.ForTHERMALPOWERlevelsbetween15%and50$ofRATEDTHERMALPOWER,deviationstheAFDoutsideofthetargetbandarelesssignificant.Thepenaltyof2hoursactualtimereflectsthisreducedsignificance.ProvisionsformonitoringtheAFDonanautomaticbasisarederivedfromtheplantprocesscomputerthroughtheAFDMonitorAlarm.ThecomputerdeterminestheoneminuteaverageofeachoftheOPERABLEexcoredetectoroutputsandprovidesanalarmmessageiftheAFDforatleast2of4or2,of3OPERABLEexcorechannelsareoutsidethetargetbandandtheTHERMALPOWERisgreaterthan90%or0.9xAPLofRATEDTHERMALPOWER(whicheverisless).DuringoperationatTHERMALPOWERlevelsbetween50%and90%or0.9xAPLofRATEDTHERMALPOWER(whicheverisless)andbetween158and50%RATEDTHERMALPOWER,thecomputeroutputsanalarmmessagewhenthepenaltydeviationaccumulatesbeyondthelimitsof1hourand2hours,respectively.ThebasisandmethodologyforestablishingtheselimitsispresentedintopicalreportWCAP-8385,"PowerDistributionControlandLoadFollowingProcedures."COOKNUCLEARPLANT-UNIT2B3/42-2AMENDMENTNO.

~YiI~Thispageintentionallyleftblank.COOKNUCLEARPLANT-UNIT2B3/42-3AMENDMENTNO.

I8*P,+lgf.I.~~1 POWERDISTRIBUTIONLIMITSBASES34.2.2and34.2.3HEATFLUXHOTCHANNELFACTORANDNUCLEARENTHALPYRISEHOTCHANNELFACTORThelimitsonheatfluxhotchannelfactor,andnuclearenthalpyrisehotchannelfactorensurethat1)thedesignlimitsonpeaklocalpowerdensityandminimumDNBRarenotexceededand2)intheeventofaLOCAthepeakfuelcladtemperaturewillnotexceedthe2200FECCSacceptance0criterialimit.EachoftheseismeasurablebutwillnormallyonlybedeterminedperiodicallyasspecifiedinSpecifications4.2.2.1,4.2.2.2,4.2.3,4.2.6.1and4.2.6.2.Thisperiodicsurveillanceissufficienttoensurethatthelimitsaremaintainedprovided:a.Controlrodsinasinglegroupmovetogetherwithnoindividualrodinsertiondifferingbymorethan+12stepsfromthegroupdemandposition.b.ControlrodgroupsaresequencedwithoverlappinggroupsasdescribedinSpecification3.1.3.6.c.ThecontrolrodinsertionlimitsofSpecifications3.1.3.5and3.1.3.6aremaintained.d.Theaxialpowerdistribution,expressedintermsofAXIALFLUXDIFFERENCE,ismaintainedwithinthelimits.FwillbemaintainedwithinitslimitsasspecifiedintheCOLRpovide%conditionsa.throughd.abovearemaintained.Therelaxationof~asafunctionofTHERMAL'POWERallowschangesintheradialpowershapeforallpermissiblerodinsertionlimits.Theformofthisrelaxationfor-DNBRlimitsisdiscussedinSection2.1.1ofthisbasis.WhenanFmeasurementistaken,bothexperimentalerrorandmanu-facturingtolerancemustbeallowedfor.5%istheappropriateallowanceforafullcoremaptakenwiththeincoredetectorfluxmappingsystemand3Sintheappropriateallowanceformanufacturingtolerance.COOKNUCLEARPLANT-UNIT2B3/42-4AMENDMENTNO.

ADMINISTRATIVECONTROLSMONTHLYREACTOROPERATINGREPORTCOREOPERATINGLIMITSREPORT6.9.1.11.1CoreoperatinglimitsshallbeestablishedanddocumentedintheCOREOPERATINGLIMITSREPORTbeforeeachreloadcycleoranyremainingpartofareloadcycleforthefollowing:a.ModeratorTemperatureCoefficientLimitsforSpecification3/4.1.1.4,b.RodDropTimeLimitsforSpecification3/4.1.3.4,c.ShutdownRodInsertionLimitsforSpecification3/4.1.3.5,d.ControlRodInsertionLimitsforSpecification3/4.1.3.6,e.AxialFluxDifferenceforSpecification3/4.2.1,,f.He'atFluxHotChannelFactorforSpecification3/4.2.2,g.NuclearEnthalpyRiseHotChannelFactorforSpecification3/4.2.3,andh.AllowablePowerLevelforSpecification3/4.2.6.6.9.1.11.2Theanalyticalmethodsusedtodetermine,thecoreoperatinglimitsshallbethosepreviouslyreviewedandapprovedbytheNRCin:a.WCAP-9272-P-A,"WestinghouseReloadSafetyEvaluationMethodology,"July1985(WestinghouseProprietary),b.WCAP-8385,"PowerDistributionControlandLoadFollowingProcedures-TopicalReport,"September1974(WestinghouseProprietary),C.WCAP-10216-P-A,PartB,"RelaxationofConstantAxialOffsetControl/FSurveillanceTechnicalSpecification,"June1983(Westingh9useProprietary),COOKNUCLEARPLANT-UNIT26-19AMENDMENTNO.

I~pl'l'1 Itv~~IIjADMINISTRATIVECONTROLSCOREOPERATINGLIMITSREPORT(Continued)e.'CAP-10266-P-ARev.2,"The1981VersionofWestinghouseEvaluationModeUsingBASHCode,"March1987(WestinghouseProprietary).6.9.1.11.3Thecoreoperatinglimitsshallbedeterminedsothatallapplicablelimits(e.g.,fuelthermal-mechanicallimits,corethermal-hydrauliclimits,ECCSlimits,nuclearlimitssuchasshutdownmargin,andtransientandaccidentanalysislimits)ofthesafetyanalysisaremet.6.9.1.11.4TheCOREOPERATINGLIMITSREPORT,includinganymid-cyclerevisionsorsupplementsthereto,shallbeprovideduponissuance,foreachreloadcycle,totheNRCdocumentcontroldeskwithcopiestotheRegionalAdministratorandResidentInspector.SPECIALREPORTS6.9.2SpecialreportsshallbesubmittedtotheRegionalAdministratorwithinthetimeperiodspecifiedforeachreport.Thesereportsshallbesubmittedcoveringtheactivitiesidentifiedbelowpursuanttotherequirementsoftheapplicablereferencespecification:a.b.ECCSActuation,Specifications3.5.2and3.5.3.hInoperableSeismicMonitoringInstrumentation,UnitNo.1,Specification3.3.3.3."c.InoperableMeteorologicalMonitoringInstrumentation,UnitNo.1,Specification3.3.3.4.d.FireDetectionInstrumentation,Specification3.3'.8.e.FireSuppressionSystems,Specifications3.7.9.1,3.7.9.2,3.7.9.3and3.7.9.4.f.SeismicEventAnalysis,Specification4.3.3.3.2.g.SealedSourceleakageinexcessoflimits,Specification4.7.8.1.3.h.ModeratorTemperatureCoefficient,Specification3.1.1.4.COOKNUCLEARPLANT-UNIT26-19aAMENDMENTNO.

I)~~4IAttachment3TOAEP:NRC:1077ASAMPLECOREOPERATINGLIMITSREPORT DONALDC.COOKNUCLEARPLANTUNIT2CYCLE7,SAMPLECOREOPERATINGLIMITSREPORTRevision0February5,1990 SAMPLECOLRforDONALDC.COOKNUCLEARPLANTUNIT2CYCLE71.0COREOPERATINGLIMITSREPORTThisisasampleCoreOperatingLimitsReportforDonaldC.CookNuclearPlantUnit2Cycle7and,therefore,hasnotbeenpreparedinaccordancewiththerequirementsofTechnicalSpecification6.9.1.11.TheTechnicalSpecificationsaffectedbythisreportarelistedbelow:3/4.1.1.43/4.1~3.13/4.1.3.43/4.1.3.53/4'.3.63/4.2.13/4.2.23/4.2.33/4.2.6ModeratorTemperatureCoefficientMovableControlAssembliesGroupHeightRodDropTimeShutdownRodInsertionLimitsControlRodsLimitsAxialFluxDifferenceHeatFluxHotChannelFactorNuclearEnthalpyRiseHotChannelFactorAllowablePowerLevelPage1of11 SAMPLECOLRforDonaldC.CookNuclearPlantUnit2Cycle72'OPERATINGLIMITSThecyle-specificparameterlimitsforthespecificationslistedinSection1.0arepresentedinthefollowingsubsections.TheselimitshavebeendevelopedusingtheNRC-approvedmethodologiesspecifiedinTechnicalSpecification6.9.1.11.2.1ModeratorTemeratureCoefficient(Specification3/4.1.1.4)2.1.1TheModeratorTemperatureCoefficientEOLLimitis:TheEOL/ARO/RTP-MTCshallbelessnegativethanthevaluegiveninFigurel.where:AROstandsforAllRodsOutEOLstandsforEndofCycleLifeRTPstandsforRatedThermalPowerHZPstandsforHotZeroThermalPower2.1.2TheMTCSurveillancelimitis:The300ppm/ARO/RTP-MTCshouldbelessnegativethanorequalto-2.9E-4Ak/k/'F.Page2ofll

~~I~,

SAMPLECOLRforDonaldC.CookNuclearPlantUnit2Cycle72.2RodDroTime,DroHeiht(Specification3/4.1.3.4)2.2.1Allrodsshallbedroppedfromatleast228steps.2.3ShutdownRodInsertionLimit(Specification3/4.1.3.5)2.3.1Theshutdownrodsshallbewithdrawntoatleast228steps.2.4ControlRodInsertionLimits(Specification3/4.1.3.6,and3/4.1.3.1)2.4.1ThecontrolbanksshallbelimitedinphysicalinsertionasshowninFigure2.2.4.2SuccessiveControlBanksshalloverlapby100steps.ThesequenceforControlBankwithdrawalshallbeControlBankA,ControlBankB,ControlBankC,andControlBankD.2.5AxialFluxDifference(Specification3/4.2.1)2.5.1TheAllowableOperationLimitsareprovidedinFigure3.2.5.2TheAXIALFLUXDIFFERENCE(AFD)targetbandduringbaseloadoperationsis+3%,-3%forcoreaverageburnup(0.0MWD/MTU.2.5.3TheAFDtargetbandis+5%,-5%forcoreaverageaccumulatedburnup>0.0MWD/MTUPage3of11 h+~~~SAMPLECOLRforDonaldC.CookNuclearPlantUnit2Cycle72.5HeatFluxHotChannelFactor-F(Z)(Specification3.2.2)CFQF(Z)<---*K(Z)QforP>0.5F(Z)<2*CFQ*K(Z)forP<0.5THERMALPOWERwhere'RATEDTHERMALPOWER2.5.1CFQ-2.10forANFfuel1.97forWestinghousefuel2.5.2K(Z)isprovidedinFigures4and5fortherespectivefueltype2.5.3V(Z)isprovidedinFigure6Page4of11

~t'~~*

SAMPLECOLRforDonaldC.CookNuclearPlantUnit2Cycle72.6NuclearEnthalRiseHotChannelFactor-F(Specification3/4.2.3)F<CFDH*(1+PFDH*(1-P))THERMALPOWERwhere:PRATEDTHERMALPOWER2.6.1CFDH-1.49forANFfuel-1.48forWestinghousefuel2.6.2PFDH-0.2forANFfuel-0.2forWestinghousefuelPage5of11 FIGURE1MODERATORTEMPERATURECOEFFICIENT(MTC)VS.VESSELAVERAGEMODERATORTEMPERATUREMTC(PCM/DEGF)-25.0-30.0-35.0MO.OM5.0545555565575VESSELAVERAGEMODERATORTEMPERATURE(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$FRACTIONOFRATEDTHERMALPOSER1.0Figure3.1~1RODBANKINSERTIONI-IMITSVERSUSTHERMALPOSERFOURLOOPOPERATION0.C.COOK-UNIT23/41-26Page7of11 y,~~.~~CI-I'I1re FIGURE3.2-1'LLO'I/ABLE.DEVIATIONFROMTARGETFLUXDIFFERENCE1120if100~80~SO-.(-.5,50}UnocjceptoOperhtion}+37~}Torge(-10,0)25.5Il)AccCptobl0peI{-aI00).{+090)+57'ionI(+2>.S)IIIIIij}(i+10.90)u'occeOperotitoblelnorge!t!nd)20OW00-20->0010f)evle<ionfroeTe<RetFluaOlfference

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

FIGURE5K(Z)-NORMALIZEDFQ(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