Revision as of 07:08, 29 June 2018

Text

Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos
	ML17335A362
Person / Time
Site:	Cook
Issue date:	12/03/1998
From:	; INDIANA MICHIGAN POWER CO.
To:	;
Shared Package
ML17335A360	List: ML17335A359; ML17335A362;
References
	NUDOCS 9812080050
	Download: ML17335A362 (142)
	v • d • e

ATTACHMENT 2ATOAEP:NRC:0433Q TECHNICAL SPECIFICATIONS PAGES'ARKEDTOSHOWPROPOSEDCHANGESUNIT1REVISEDPAGES3/40-33/43-2la3/44-383/44-403/47-153/49-13/49-135-65-7b6-49812080050 981203PDRADOCK05000815PPDR

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34.0APPLICABILITY SURVEILLANCE REUIREMENTS b.Surveillance intervals specified inSectionXIoftheASMEBoilerandPressureVesselCodeandapplicable Addendafortheinservice inspection andtestingactivities requiredbytheASMEBoilerandPressureVesselCodeandapplicable Addendashallbeapplicable asfollowsintheseTechnical Specifications:

ASMEBoilerAndPressureVesselCodeandapplicable AddendaRequiredfrequencies forterminology forinservice performing inservice inspec-inspection andtestingcriteriationandtestingactivities WeeklyMonthlyQuarterly orevery3monthsSemiannually orevery6monthsYearlyorannuallyAtleastonceper7daysAtleastonceper31daysAtleastonceper92daysAtleastonceper184daysAtleastonceper366daysc.Theprovisions ofSpecification

4.0. 2areapplicable

totheaboverequiredfrequencies forperforming inservice inspection andtestingactivities.

d.Performance oftheaboveinservice inspection andtestingactivities shallbeinadditiontootherspecified Surveillance Requirements.

e.,NothingintheASMEBoilerandPressureVesselCodeshallbeconstrued tosupersede therequirements ofanyTechnical Specification.

4.0.6endments$00,107and108grantedextensions orceransueillanckrequiretobeprformednorbeforeJuly31,1987,andtiltheendofeCycle-10refulingoutage.orthesespecicsurvelancesderthisection,thesPcifiedimeintervarequirdbySpeificatio4.0.2wllbetermindwiththenewitiationdateesblishedytheseillacedateduringtheUnit1987refuelinoutae.4.0.7eneeannsurveysanctobeperfoedonobeforepril1,1989,untiltheendoftheCyc10-11fuelingutage.Forthespecicsueillanesunderthisextsion,tpspeciedtiintervsreqiredbSpecifiation4.2willbqdetenedwxhthenqiniationestablisdbytheurveillance datedurintheUn'189refueling

'outteCOOKNUCLEARPLANT-UNIT13/40-3AMENDMENT NO.ggg<</gal<<144 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE3.3-3Continued ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION FUNCTIONAL UNIT6.MOTORDRIVENAUXILIARY FEEDWATER PUMPSMINIMUMTOTALNO.OFCHANNELSCHANNELSAPPLICABLE CHANNELSTOTRIPOPERABLEMODESACTIONa.SteamGenerator WaterLevel-Low-Low3/Stm.Gen.2/Stm.Gen.2/Stm.Gen.anyStm.Gen.1,2,314b.4kvBusLossofVoltagePumpStartValveActuation (Bothtrains)c.SafetyInjection d.LossofMainFeedwater Pumps7.TURBINEDRIVENAUXILIARY FEEDWATER PUMPS3/Bus2/Bus2/bus(TlIA-TrainB;T11D-TrainA)2/buson(TlIA8cT11Bor2/bussesTllc&T11D),2/Bus1,2,31,2,31,2141818a.SteamGenerator 3/Stm.Gen.WaterLevel-Low-Lowb.ReactorCoolantPump4-1/BusBusUndervoltage 8.LOSSOFPOWERa.4kvBusLossof3/BusVoltage2/Stm.Gen.any2Stm.Gen.2/Bus2/Stm.Gen.2/Bus1,2,31,2,31,2,3,4141914b.4kvBusDegraded3/BusVoltage(Ttl8TraInljatt)-Tr~'~h)2/Bus2/BusI,2,3,4(Ttth-TrRI'~Sj (rttA-7~:~8>

Yttb-frai~h) sub-T~t~h) 14COOKNUCLEARPLANT-UNIT 1Page3/43-21aAMENDMENT

$C,~,153 4.4.$2.1BothReactorVesselheadventpathsshallbedeaanstrated OPI',RABleastonceper18monthsby:1.Verifying theccmaaamanualisolation valveintheReactorvesselheadventissealedintheopenposition.

2.CyclingeachoftheremotelyoperatedvalvesinesohpaththroughatleastonecompletecycleoffulltraveltreetheControlRocNawhileinBodes5or6.3~Verifying floethroughbothoftheReactorVesselheadventpathsduringvaat~operation, awhileinBodes5or6.AeQ.lance equiraaen todemonsatetheoperilityofeaceactorVelheadvepathvQ,leperformed henexttimeeunitentersHES5or6IlyingthissuanceofhisTechnical spec1r1tion,andortheappprtateplprccednrea peebeenvritten.D.CCOOK-UNITl3/44-38 4.4.$g.2Bothsurisers~eaaspaceveatpathsshallbedeneastrated 0?atleastoacepec18centhsbycf.Verifying thecommaaaaualisolation valvoiathePressurizer st04$spaceventissealediatheopenyoaitioao CyoliageachofthereaetelyoperatedvalvesineachyaththroughatleastoaeooapletecycleoffulltravelfroathoCoatrolRooe~einHades5or6.3.Verifying flamthroughbothofthePressurizer steaasycLcerentyaths4uriagveatiagoperation,

~lein}fedos5oc'.illanoereqantsto4nstratet~operabiyofeachPrurerstespaceveatthWllbperfothenextttheteatersES5oc'floviagthessuaaoethisTechaiySpeed.fkcati9, aadaftereapproprtePlantrocedures hag@beene'ittea./D~CoCOOK3/44-40Aaaadmeat ceo.98 C

3.7.3.1OOLGVTE00ERATIOa.Atleasttwoindependent component coolingwaterloopsshallbeOPERABLE.

MLb.Atleastwncecomponent coolingwaterflowpathinsupportofUnit2shutdownfunctions shallbeavailable.

Specification 3.7.3.1.b

-AtalltimeswhenUnit2isinMODES1,2,3,or4.~CT~IOV&bhSpecification 3.7.3.1.a isapplicable:

Vithonlyonecomponent coolingwaterloopOPERABLE, restoreatleasttwoloopstoOPERABLEstatuswithin72hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WhenSpecification 3.7.3.1.b isapplicable:

WithnoflowpathtoUnit2available,

'returnatleastoneflowpathtoavailable statuswithin7days,orprovideequivalent shutdowncapability inUnit2andreturnatleastoneflowpathtoavailable statuswithinthenext60days,orhaveUnit2inHOTSTANDBYwithinthenext12,hoursandHOTSHUTDOWN.withinthefollowing 24hours.Therequirements ofSpecification 3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.7.3.1Atleasttwocomponent cooling.waterloopsshallbedemonstrated OPERABLE'.

Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) servicing safetyrelatedequip-mentthatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.

b.Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveservicing safetyrelatedequipment actuatestoitscorrectpositiononaSafetyIn]ection testsignal.c.Byverifying pumpperformance pursuanttoSpecification 4.0.5.d.Atleastonceper18monthsduringshutdown, byverifying thatthehcross-tievalvescancyclefulltravel.Pollowing cycling,thevalveswillbeverifiedtobeintheirclosedpositions.

COOKNUCLEARPLANT-UNIT13/47-15AMENDMENT NO.447,434,444,164 rII G0OROCONCELIMITINGCONDITION FOROPERATION 3.9.1Withthereactorvesselheadunbol'ted orremoved,theboronconcentration ofallfilledportionsoftheReactorCoolantSystemandtherefueling canalshallbemaintained uniformandsufficient toensurethatthemorerestrictive ofthefollowing reactivity conditions ismet:a.EitheraKffof0.95orless,whichincludesa1%Jc/k.effconservative allowance foruncertainties, orb.Aboronconcentration ofgreaterthanorequalto2400ppm,whichincludesa50ppmconservative allowance foruncertainties.

~CT~OWiththerequirements oftheabovespecification notsatisfied, immediately suspendalloperations involving COREALTERATIONS orpositivereactivity changes~+

andinitiateandcontinueborationatgreaterthanorequalto10gpmof20,000ppmboricacidsolutionoritsequivalent untilKfisreducedefftolessthanorequalto0.95ortheboronconcentration isrestoredtogreaterthanorequalto2400ppm,whichever isthemorerestrictive.

Theprovisions ofSpecification 3.0.3arenotapplicable.

SURVEILLPSCE REUIREMENTS 4.9.1.1Themorerestrictive oftheabovetworeactivity conditions shall'oedetermined priorto:a.Removingorunbolting thereactorvesselhead,andb.Withdrawal ofanyfulllengthcontrolrodinexcessof3feetfrom'itsfullyinsertedposition.

4.9.1.2Theboronconcentration of,thereactorcoolantsystemandthe~~~it~Mxi72hours.0ACe.pe,r*Thereactorshallbemaintained inMODE6whenthereactorvesselheadisunboltedorremoved.*~Forpurposesofthisspecification, additionofwaterfromtheRWSTdoesnotconstitute apositivereactivity additionprovidedtheboronconcentration intheRWSTisgreaterthantheminimumrequiredbySpecification 3.1.2.7.b.2.

D.C.COOK-UNIT13/49-1AMENDMENT NO.

~~c'~l3,9.12Thespentfuelstoragepoolexhaustventilation systemshallbeOPERABLE.

Wheneverirradiated fuelisinthestoragepool.a~Withnofuelstoragepoolexhaustyentilati.on systemOPERABLE, suspendalloperations involving movementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepooluntilatleastonespentfuelstoragepoolexhaustventilation systemisrestoredtoOPERABLEstatus.*b.Theprovisions ofSpecificati'ons 3.0.3and3.0.4arenotapplicable.

'4C4.9.12Theaboverequiredfuelstoragepoolventilation systemshallbetdemonstraied OPERABLE:

a.Atleastonceper31daysbyinitiating flowthroughtheHEPAfilterandcharcoaladsorbertrainandverifying thatthetrainoperatesforatleast15minutes.Atleastonceper18monthsor(1)afteranystructural.

maintenance ontheHEPAfilterorcharcoaladsorberhousings, or(2)following

painting, fireorchemicalreleaseinanyventilation zonecommunicating withthesystem,by:1.Deleted.2.Verifying thatthecharcoaladsorbers remove>99%ofahalogenated hydrocarbon refrigerant testgaswhentheyaretestedin-placeinaccordance withANSIN510-1980 whileoperating theexhaustventilation systemataflowrateof30,000cfm+10%.5ovooryeovxfli(hlovi14nc~(aN8~+7*Thecranebayroll-updoorandtherunua&g-room-rcrH~~oer maybeopenedunderadministrative controlduringmovementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepool,~SharedsystemwithD.C.COOK-UNIT2.~~Thisdoesnotincludethemainloadblock.Forpurposesofthisspecification, adeenergi"ed mainloadblockneednotbeconsidered aload.D.C.COOK-UNIT13/49-13Amendment No.1~4 I

5.0DESIGNFEATURES5.6FUELSTORA EContinued Region1isdesignedtoaccommodate newfuelwithamaximumnominalenrichment of4.95wt%U-235,orspentfuelregardless ofthedischarge fuelburnup.2.Region2isdesignedtoaccommodate fuelof4.95%initialnominalenrichment burnedtoatleast50,000MWD/MtU,orfuelofotherenrichments withequivalent reactivity.

3.Region3isdesignedtoaccommodate fuelof4.95%initialnominalenrichment burnedtoatleast38,000MWD/MtU,orfuelofotherenrichments withequivalent reactivity.

Theequivalent reactivity criteriaforRegion2andRegion3isdefinedviathefollowing equations,'nt+raphicalbpdepieted-i~re-5

~MinimumAssemblyAverageBurnupinMWD/MTU=-22,670+22,220E-2,260E+149E3MinimumAssemblyAverageBurnupinMWD/MTU=-26,745+18,746E-1,631E+98.4E3WhereE=InitialPeakEnrichment 5.6.1.2:Fuelstoredinthespentfuelstorageracksshallhaveamaximumnominalfuelassemblyenrichment asfollows:Description MaximumNominalFuelAssemblyEnrichment Wt.%U-2351)Westinghouse 2)Exxon/ANF 3).Westinghouse 4)Exxon/ANF 15x15STD15x15OFA15x1517x17STD17x17OFA17x17V517x174.954.95'.954.95COOKNUCLEARPLANT-UNIT 1Page5-6AMENDMENT SV,436,4N,44&,213 egonsIrQXC4.Q~~~COO1>eeocIr~'CC'CCC::SCHMOCLIOOOOrrrSXOOOAc)I"-IoUR.P9QMiNIJH""OABLE3URN'DCM+Hl2.0~S.O!NGl4.-IRIPIMEHT.

aU-235CWGKi'~

6.0 ADMINISTRATIVE

CONTROLS**""Q**'"

6.3.1Eachmemberofthefacilitystaffshallmeetorexceedtheminimumqualifications ofANSIN18.1-1971 forcomparable positions, exceptfor(1)thePlantRadiation Protection Manager,whoshallmeetorexceedqualifications ofRegulatory Guide1.8,September 1975,(2)theShiftTechnical Advisor,whoshallhaveabachelor's degreeorequivalent inascientific orengineering discipline withspecifictraininginplantdesign,andresponseandanalysisoftheplantfortransients andaccidents and,(3)theOperations Superintendent, whomustholMr-htt~eld-a-Senier-Operatm-license asspecified inSection6.2.2P..eva.tig)t.46.4TRAININGt;<;6.4.1Aretraining andreplacement trainingprogramforthefacilitystaffshallbemaintained underthedirection oftheTrainingManagerandshallmeetorexceedtherequirements andrecommendations ofSection5.5ofANSIN18.1-1971 and10CFRPart55.5.5REVIEWANDAUDIT6.5.1PLANTNUCLEARSAFETYREVIEWCOMMITTEE PNSRCFUNCTION6.5.1.1ThePNSRCshallfunctiontoadvisetheSiteVicePresident/Plant Manager,ordesignee, onallmattersrelatedtonuclearsafety.COMPOSITION 6.5.1.2ThePNSRCshallbecomposedofAssistant PlantManagers, Department Superintendents, orsupervisory personnel reporting directlytotheSiteVicePresident/Plant Manager,Assistant PlantManagersorDepartment Superintendents.

Themembership shallrepresent thefunctional areasoftheplant,including, butnotlimitedtnOperations, Technical Support,Licensing, Maintenance andRadiation Protection ThePNSRCmembership shallconsistofatleastoneindividual fromeachoftheareasdesignated.

Allmembers,including theChairmanandhisahemates, themembersandtheiralternates, shallbedesignated bytheSiteVicePresident/Plant Manager.PNSRCmembersandalternates shallmeetorexceedtheminimumqualifications ofANSIN18.1-1971Section4.4forcomparable positions.

Thenuclearpowerplantoperations individual shallmeetthequalifications ofSection4.2.2ofANSIN18.1-1971 exceptfortherequirement toholdacurrentSeniorOperatorLicense.Theoperations individual mustholdorhaveheldaSeniorOperatorLicenseorhavebeencertified forequivalent senioroperatorknowledge atCookNuclearPlantorasimilarreactor.Themaintenance individual shallmeetthequalifications ofSection4.2.3ofANSIN18.1-1971.

COOKNUCLEARPLANT-UNIT 1Page64AMENDMENT 49,4B)48K,454)486)4Q)212 ATTACHMENT 2BTOAEP:NRC:0433Q TECHNICAL SPECIFICATIONS PAGESMARKEDTOSHOWPROPOSEDCHANGESUNIT2REVISEDPAGES3/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/40-30-43-113-203-303-313-343-44d3-474-134-144-334-354-375-45"86-126-146-477-127-137-16a7-208-98-138-159"125-65-86-4 34AAPPLICABILITY SURVEILIANCE REUIEUUKNTS b.Surveillance Intervals specified inSectionXIoftheASMEBoilerandPressureVesselCodeandapplicable Addendafortheinservice inspection andtestingactivities xequired'y theASMEBoilerandPressureVesselCodeandapplicable Addendashallbeapplicable asfollow'siatheseTechnical Specifications:

ASMEBoilerAndPressureVesselCodeandapplicable-Addenda terminology forinservice insectionandtestincriteriaRequiredfrequencies forperforming inservice inspec-tionandtestinactivities

'od.WeeklyAtleastonceper7daysMonthlyAtleastonceper31days~rterlyorevery3monthsAtleastonceper92daysSemiannually orevery6months,Atleastonceper184daysYearlyorannuallyAtleastonceper366daysTheprovisions ofSpecification

4.0. 2axeapplicable

totheabove'required frequencies forperforming insexvice inspection andtestingactivities.

Performance oftheaboveinservice inspection andtestingmctivities shallbeinadditiontootherspecified Surveillance Requirements.

e~4.0.6NothingintheASMEBoilerandPressureVesselCodeshallbecon-stxuedtosupersede therequirements ofanyTechnical Specification.

'ba,enganeeensonsorcernsurveancesrequiredtobeperormedgnorbefreMarh31,186,untitheendoftheCyc~e5-6efueliilg outageFor'sespcificseillanc)underthisectiothes$cifiedtimeinexvalsequiredySpecicatio4.0.2illbedetermiedwiththenenitia)ondateestablisedbtheurveilancedaedurintheUnit21984refuoutae.4.0.7Amendments 97and99grantedextensions forcertanreuiredtoeperformdonorbereJuly~1,1988,untiltheendofthCycle6-refueling utage.Fothesehecificseillanesundethissecon,thesecifiedteintelsrequirdbySpecication4..2willbedetermine withthnewinitationteestabli+edbythesurveilla cedatedngtheit219refueling outage.COOKNUCLEARPLANT-UNIT23/40-3AMENDMENT NO.7g,g7,131 1't) 340LXCSURVEILLANCE 4.0.8Byspecificreerencetossecton,osesurveanceswhichmustbeprformedonorbeforehut13,1994,andaredesignedas-monthr36-mosurvelancesorreedasouge-related seillansundetheprosionsoSpecifiation4..5)maybedeledunttheenofthecl'e9-10efuelioutage.Forthesespecicseillancsunderthissetion,speciiedtimeintelsreredbypecificaion4.0.willbdetermedwiththeneinitiatondatestablishdbythesurveillcedatduringth'eUnit21994efuelinoutae.4.0.9Byspecificreerencetossecton,osesurveanceswhi.chmusbeperformed onbeforeeptembr7,194,andadesitedas1monthh~eillanesmayedeladuntijustprortoreeloadnthetJqit2Cye9-10efuelioutaCOOKNUCLEARPLANT-UNIT23/40-4AMENDMENT NO.~,166 nOTB.E3-CTORISYSTSTE0SVCUFUNCTIONAL UNI1.ManualReactorTripA.ShuntTripFunctionB.Undervoltage TripFunction2.PowerRange,NeutronFlux3.PowerRange,NeutronFlux,HighPositiveRate4.PowerRange,NeutronFlux,HighNegativeRate5.Intermediate Range,NeutronFluxCHANNEL~GEEN.A.N.A.N.A.N.A.CHANNELC0N.A.N.A.(20)IM(I)andQ(608)R(6)R(6)'(6,8)CHANNELFUNCTIONAL

~AT.~S/U(1)(10)S/U(1)(10)MandS/U(l)S/U(l)MODESINWllICHSURVEILLANCE RUR3*,4*,5*3*,4*,5*1,2and*1,21,21,2and*aWo6.SourceRange,NeutronFlux7.Overtemperature AT8.Overpower AT9.Pressurizer Pressure--Low 10.Pressurizer Pressure--High ll.Pressurizer WaterLevel--High 12.LossofFlow-SingleLoopR(6,14)R(9)gR(9)e"ReRPaQR(8)M(14)andS/U(l)2(7),3(7),4and51,21,21,21,~21,2 r>t0 TABLE3.3-3Continued ENGINEERED SAFETYFEATURESACTUATION SYSTEMINSTRUMENTATION FUNCTIONAL UNITMINIMUMTOTALNO.CHANNELSCHANNELSAPPLICABLE OFCHANNELSTOTRIPOPERABLEMODESACTION7.TURBINEDRIVENAUXILIARY FEEDWATER PUMPStfla.SteamGenerator WaterLevel--Low-Low 3/Stm.Gen.2/Stm.2/Stm.1,2,3Gen.anyGen.2Stm.Gen.14*b.ReactorCoolantPumpBusUndervoltage 8.LOSSOFPOWERI4-1/Bus1,2,319*a.4kVBusLossofVoltage3/Bus2/Bus2/Bus1,2,3,414*b.4kVBusDegradedVoltage9~MANUAL3/Bus(QiA-(nfl'i721l)VIE+Qj2/Bus2/Bus1,2,3,414*(T7lbTmlnBj(T2lATm'+SiTz,ID-Twi<<)T't<D-<~'<4)a.SafetyInjection (ECCS)Feedwater Isolation ReactorTrip(SI)Containment Isolation-Phase"A"Containment PurgeandExhaustIsolation Auxiliary Feedwater PumpsEssential ServiceWaterSystem2/train1/train2/train1,2,3,418b.Containment SprayContainment Isolation-Phase"B"Containment PurgeandExhaustIsolation Containment AirRecirculation Fan1/train1/train1/tra'in1,2,3,418c.Containment Isolation-Phase"A"Containment PurgeandExhaustIsolation 1/train1/train1/train1,2,3,418d.SteamLineIsolation 2/steam2/steamline(1line(1pertrain)pertrain)2/opera-1,'2,3tingsteamline(1pertrain)20COOKNUCLEARPIANT-UNIT23/43-20AMENDMENT NOg7jfgg~137' 3/4..LIMI'HNGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE4.3-2ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION SURVEILLANCE REUIREMENTS FUNCTfONAL UNITl.SAFETYINIECIION, TURBINETRIP,FEEDWATER ISOLATION.

ANDMOTORDRIVENAUXILIARY FEEDWATER PUMPSCHANNELCfiANNELCHANNELFUNCTIONAL CHECKCALIRAIIDHIEEI'RIPACTUATING DEVICEOPERATIONAL MODESINWHICHSURVEILLANCE SQUIREDa.ManualInitiation b.Automatic Actuation Logicc.Containm<<nt Pressure-Highd.Pressurixcr Prcssurc-Lowc.DifFerential PressureBctwccnSteamLines-Highf.StcamLuePressure-Low2.CONTAINMENT SPRAYa.ManualInitiation b.Automatic Actuation Logicc.Concunmcnt Pressure-High.High3.CONTAINMENT ISOLATION a.Phase'AIsolation N.A.N.A.N.A.N.A.M(3)N.A.N.A.N.A.N.A.SceFunctional Unit9M(2)N.A.M(3)N.A.SccFunctional Unit9M(2)N.A.I,2,3,41,2,3I,2,3I,2,31,2,31,2,3,41,2,3I)Manual2)FromSafetyInjection Automatic Actuation Logic'.PhaseB'solation N.A.N.A.SccFunctional Unit9M(2)N.A.1,2,3,4I)Manual2)Automatic Actuation Logic3)Containmcnt Pressure-f{igh.HighN.A.SSccFunctional Unit9M(2)M(3)N.A.N.A.1,2,3,41,2',3COOKNUCLEARPLANT-UNIT 2Pago3/43-30AMENDMENT 34,434,4K,158 CJ 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE4.3-2Continued ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION SURVEILLANCE REUIREMENTS FUNCTIONAL UNITc.PurgeandExhaustIsolation CHANNELCHANNELCHANNELFUNCTIONAL CHECKCALIBRATION TESTlTRIPACTUATING DEVICEOPERATIONAL TESTMODESINWHICHSURVEILLANCE

~REUlREDI)Manual2)Containment Radioactivity

-HighSccFunctional Unit9-N.A.1,2,3,44.STEAMLINEISOLATION a.Manual-SecFunctional Unit9--b.Automatic Actuation Logicc.Containmcnt Pressurc-High-High d.SteamFlowinTwoSteamLines-HighCoincident withT,,-Low-Lowc.SteamLinc'Prcssurc-LowS.TURBINETRIPANDFEEDWATER ISOLATION a.SteamGenerator WaterLevel-High-High N.A.N.A.M(2)M(3)N.A.N.A.N.A.N.A.N.A.I,2,3I,2,3I,2,31,2,31,2,36.MOTORDRIVENAUXILIARY FEEDWATER PUMPSa.StcamGenerator iVaterLevel-Low-Lowb.4kVBusLossofVoltagec.SafetyInjection d.LossofMainFeedPumpsN.A.N.A.N.A.N.A.M(2)N.A.N.A.I,2,3I,2,3I,2,31,2"%teart)vhion~~tnicaLSpcciiieatiea-4A)A Ltpplicable.

COOKNUCLEARPLANT-UNIT 2Page3/43-31AMENDMENT aI,&,434,434,4W,459,16S Pk0 3/4.3.3KOH~~OEIHC GiSTM~LTION LXKKTZSCCOHDZTZOS FOEQPKLLTIQS 3.3.3.1Thara~~~mcraiarz~

~~~mantas~mn

~mn~ahcncnTahoe3.~ahaU.beQPKLL'.KZ

~~~/~sespo~W~the)spec'~~~4CXEZLZZT:

haabc'Tabb<3.~.JCXZOE:a.V'Aa~~non'~~channelakaxa/a~aespoinsczcaa~thavaLaasheewTable3.M,adgnos~aetpo~toMahdithaXfad.tW~4boersorde~athachannelfmoperabIa.

bo%~AoneoTnccet~~~celt?ftoT~

ch@nL'eezabla,rakethe~HebcncafaTabl.a3.~.c.Thepmvta~ofSpe~caeLana 3.0.3cad3.0.4arenotapylfcabLa.4.3.3.1EachzmLfaahan zoon"metalc1nnuaakahaLlbeasshefx'eqnencMs abneriaTabLa4.33.~i~ehQca1~H4ng-osage D,C.CQOK~23/4334A$EtldQolTC

)f0~43 riOOc<riXuasauumr:

ir1.SteamGenerators 1and4LevelV000GV~GVES¹LE~041CabinetlandLSICabinet4ClhNNEL~CWCQCllANNELC02,SteamGenerators 2and3LovelLSICabinet2andLSICabinet43.SteamGenerators 1and4ProssureLSICabinet4andLSICabinet5SteamGenerators 2and3PressureLSICabinet4andLSICabinet65,ReactorCoolantLoop4Temperature (Cold)6.ReactorCoolantLoop4Temperature (llot)LSICabinet4andLSICabinet5LSICabinet4andLSICabinet5Ry)7,ReactorCoolantLoop2Temperature (Cold)LSICabinet4andLSICabinet68.,RoactorCoolantLoop2Temperature (llot)LSICabinet4andLSICabinet6eg09.Pressurizer Lovel.10.RaactorCoolantSystemPressurell.ChargingCross-Flow BetweenUnitsLSICabinet3LSICabinet3gorridorKiev.587'/aR'2.SourceRangeNeutronDetector(N-23)LSICabinet4n/a*CbargingGross-1'low betweenUnitsisaninstrpment commonto'bothUnit1and2,Tbissurveillance villonlyboconducted onanintervalconsistent MithUnit1refueling.

wuhlI r>

BL3-0OS-COlTORINGSEAT00VUEECJNNHEL~CEEC1.2~3~4,5.6.7~8.9.10'1.12~13.14.15.16.17~1B.Containment PressureReactorCoolantOutletTemperature

-Tgp)(HideRange)ReactorcoolantInletTemperature

-T<<,p(HideRange)ReactorCoolantPressure-HideRangePressurizer WaterLevelSteamLinePressureSteamGei>orator HaterLevel-NarrowRangeBHSTWaterLevelBoricAcidTankSolutionLevelAuxiliary Feedwater FlowRateReactorCoolantSystemSubcooling MarginMonitorPORVPositionIndicator

-LimitSwitchesPORVBlockValvePositionIndicator

-LimitSwitchesSafetyValvePositionIndicator

-AcousticMonitorIncoreThermocouples (CoreExitThermocouples)

ReactorCoolantInventory TrackingSystem(ReactorVesselLevelIndication)

Containment SumpLevelContainment HaterLevelMMMMMMMMMMMMMMMM(2)MMR+RRRRRR(1)%'(3)P RPartialrangechannelcalibration forsensortobeperformed belowP-12inMODE3.(2)(3)HithonetrainofReactorVesselLevelIndication inoperable, Subcooling MarginIndication andCoreExitThermocouples maybeusedtoperformaCHANNELCHECKtoverifytheremaining ReactorVesselIndication trainOPERABLE.

Completion ofchannelcal'ibration forsensorstobe.performed belowP-12inMODE3.COOKNUCLEARPLANT-UNIT23/43-47AMENDMENT NO.'9&E9S,

~>

CDnCDCD7C1STSAMPLE.1NSPECTlON TABLE4.4-2STEAMGENERATOR TUBEtNSPECTION 2NDSAMPLElNSPECTION 3ADSAMPLEINSPECTION SaintitoSireAcauliActicinltcituircd ResultAcriuntt'oquircd AcauliAclionAcquucdAminunumolSTubestierS.G.C-1C-2C-3NuiiePtuadclcclive lubcaandlnspecledititionat 2SlubestnllusS.G.tnstiectalltutiesrnttuaS.G..l)lugUelocllvetubesaililtnsticct2SlubesincactiotlicrS.G.Promtllnultticallon toNACpursuanttospecilication 69.1NIAC-1C-2C-3AtlalberSGiseicClSameS.G.sC-2butnoadditional S.G.aieC-3Additional S.G.iaC-3NIANnnePhag'detective tubesaiidiniticclaitititianat 4StubesuiltwsS.G.PciloimaclioiilorC-3resultollullaamtiteNonePcilormac(iantbrC-2resultolsecondtnspoctalllubeaineachS.G.andpkrydelectivetubes.Promptnolilicatlon loNRCpursuantlospecilicalian G.Q.IN/ANIAC-1C-2NIANIANIANIANIANoneNIANIANIANIANIAPtugdetective lulieaPcrloimactiontorC-3resultollustsamtite3N<ShoreHlatlienumberolstcamttaneratora tnlheunit,anditlslhenumberolsteamtteneiatora

<<specteriluitnQJntnrtioctlon C

REACTORCOOLANTSYSTEM3/4.4.6REACTORCOOLVPPSYSTEMLLQCAGEL~QCAGEDETECTION SYSTEMSLIMITINGCONDITION FOROPERATION 3.4.6.1Thefollowing ReactorCoolantSystem,leakagedetection syseemsshallbeOPERABLE:

a.Oneofthecontainmene atmosphere particulate radioactivity monitoring'hannels (ERS-2301 orERS-2401),

b.Thecontainment sumplevelandflowmonitoring system,andc.Eitherehecontainmene humiditymonitororoneofthecontainmene atmosphere gaseousradioactivity monitoring channels(ERS-2305 orERS-2405).

APPLICABILITY:

MODES1,2,3and4ACTION'ith onlytwooftheaboverequiredleakagedetection systemsOPERABLE, operation mayconeinueforupto.30daysprovidedgrabsamplesofthecontainmene atmosphere areobtainedandanalyzedatleaseonceper24hourswhen~~~~eherequiredgaseousand/orparticulate radioactivity monieoring channelsareinoperable; otherwise, beinatleaseHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwiehinehefollowing 30hours.SURVEILLANCE REUIREMENTS 4.4.6.1Theleakagedetection systemsshallbedemonserated OPERABLEby:a~Containment atmosphere particulate andgaseous(ifbeingused)monitoring system-perfonnance ofCHANNELCHECK,CHANNELCALIBRATION andCHANNELFUNCTIONAL TESTatthefrequencies specified inTable4.3-3,b.Containmene sumplevelandflowmonitoring syseem-performance ofCHANNELCALIBRATION aeleastonceper18months,c~Containmene humidieymonitor(ifbeingused)-performance ofCHANNELCALIBRATION aeleaseonceper18"months.

COOKNUCL<<RPLANT-UNIT23/44-14AMENDMENT NO.W,~,159 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE RE<QUIRL<MI<

NTS('/4.4REACTORCOOLANTSYSTEMREACTORCOOLANTSYSTEMLIMITINGCONDITION FOROPERATION Continued WithPORVsandblockvalvesnotinthcsamelineinoperable duetocausesotherthanexcessive seatleakage,within1hourrestorethevalvestoOPERABLEstatusorcloseanddc-energize theassociated blockvalveandplacetheassociated PORVinmanualcontrolineachrespective line.ApplytheportionsofACTIONcordabove,relatingtotheOPERATIONAL MODE,asappropriate fortwoorthreelinesunavailable.

h.Theprovisions ofSpecification 3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.4.11.1Inadditiontotherequirements ofSpecification 4.0.5,eachPORVshallbcdemonstrated OPERABLE:

Atleastonceper31daysbyperformance ofaCHANNELFUNCTIONAL TEST,excluding valveoperation, andAtleastonceper18monthsbyoperating thePORVthroughonecompletecycleoffulltravelduringMODES3or4,andc.Atleastonceper18monthsbyoperating solenoidaircontrolvalvesandcheckvalvesinPORVcontrolsystemsthroughonecompletecycleoffulltravel,andAtleastonceper18monthsbyperforming aCHANNELCALIBRATION ofthcactuation instrumentation&

4.4.11.2Eachblockvalveshallbcdemonstrated OPERABLEatleastonceper92daysbyoperating thevalvethroughonecompletecycleoffulltravelunlesstheblockvalveisclosedinordertomeettherequirements ofACTIONb,c,ordinSpecification 3.4.11.4.4.11.3Deleted.f-'Feehnieal-Speei6eatie licable.COOI(NUCLEARPLANT-UNIT 2Page3/44-33AMENDMENT 4W,~,4W,444,196 it

'~4~~4.4.12.1BothReactorVesselheadventpathsshallbedeaanstrated OPEleastonceper18monthsby:Verifying thecommonmanualisolation valveintheReactorvesselheadventissealedintheopenposition.

2.CyclingeachoftheremotelyoperatedvalvesineachpaththroughatleastonecompletecycleoffulLtravelfromtheControlRoomwhileinNodes5or6~3.Verifying floethroughbothoftheReactorVesselheadventpathsduringventingoperation, awhileinNodes5or6.Surveillan erequintstodnstratethe,operabilit ofeacheactorVeselheadvetpathbeperfoHthenextimetheuttersNOD5or6folingthesuanceofTechnicSpfication, andafterheapproprtePlantpcedureshaebeenm'iten.D.C.COOK-terr23/44-35amencunent Wo.65 r>

4.4.12.2BethPrsurizersteamspaceventpathsshallbedemonstrated OPBKLBLatleastonceper18monthsby:1~Verifying thecommonmanualisolation valveinthePressurizer steamspaceventissealedintheopenposition.

CyolingeachofthereaetelyoperatedvalvesineachpaththroughatleastonecompletecycleoffulltravelfromtheControlRoomwhileinModes5or6.3.Verifying flowthroughbothofthePressurizer steamspaceventpathsduringventingoperation, whileinModes5or6.rISurveill+ce requireme todemotratethepdrability ofhPressurizer steamspeventpawillbeformedthentimeHeunitenersMODES5or6folingtheiuanceoftechnicSpeoifgcation, anafterthappropria Plantproceshaveenwritt~~0.C.COOK-UHZT23/44-37Amenchnent No.65 EMERGENCY CORECOOLINGSYSTEMS~~SURVEILLANCE REUIREMENTS 4.5.2EachECCSsubsystem shallbedemonstrated OPERABLE:

a.At1'eastonceper12hoursbyverifying thatthefollowing valvesareintheindicated positions withpowertothevalveoperators removed:ValveNumberValveFunctionValvePositiona.IMO-390b.IMO-315c.IMO-3250d.Q-262*e.IN-263*f.IMO-261*g.ICM-305*h.ICM-306*a.RWSTtoRHRb.LowheadSItoHotLegc.LowheadSItoHotLegd.Miniflowlinee.Miniflowlinef.SISuctiong.SumpLine,h.SumpLinea.Openb.Closedc.Closedd.Opene.Openf.Openg.Closedh.Closedb.Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic}

intheflowpaththatisnotlocked,sealed,or~othersesecuredinposition, isinitscorrectposition.

c.Byavisualinspection whichverifiesthatnoloosedebris(rags,tx'ash,clothing, etc.}ispresentinthecontainment whichcouldbetransported tothecontainment sumpandcauserestriction ofthepumpsuctionsduringLOCAconditions.

Thisvisualinspection shallbeperformed:

1."Forallaccessible areasofthecontainment priortoestablishing CONTAINMENT INTEGRITY, and2.Oftheareasaffe'cted withincontainment atthecompletion ofeachcontainment entrywhenCONTAINMENT INTEGRITY isestablished.

esevalvesmustchangepositionduringtheswitchover frominjection torecirculation flowfollowing LOCA.COOKNUCLEARPLANT-UNIT23/45-4AMENDMENT N0.7$,$3$

eeGENCYCORCOOLGSSSURVe.ELLANCE RCc.5.3elTheECCSsubsystem shallbedemonstrated OPERABLEpertheapplicable

~~Sn~eillence Reqnizenence e=4.5.2.Oe.

4.5.3.2Allchargingpumpsandsafetyin]ection pumps,excepttneaboverequiredOPERABLEchargingpump,shallbedemonstrated inoperable, byverifying thatthemotorcircuitbreakershavebeenremovedfromtheirelecMcalpo~ersupplycircuits, atleastonceper12hoursvheneverthetemperature ofoneormoreof"theRCScoldlegsislessthanorequalto152Fasdetermined atleastonceperhour~henanyRCScoldlegtemperature isbetween152'Fand200F.vCOOKHUCLZARPLANT-UNXT23/c&5-8 COSYSSURVEILLANCE EREMENTSCotinuedC~Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveintheflowpathactuatestoitscorrectpositiononaContainment Pressure--High-High testsignal+.d.Atleastonceper5yearsbyverifying awaterflowrateofatleast20gpm(greaterthanorequalto20gpm)butnottoexceed50gpm(lessthanorequalto50gpm)fromthesprayadditivetanktestlinetoeachcontainment spraysystemwiththespraypumpoperating onrecirculation withapumpdischarge pressuregreaterthanorequalto255psig.chnM~peci-re-appkkcab1e.

COOKNUCLEARPIANT-UNET2~3/46-12AMENDMENT NO.4SgMf48k)15

CONTAINMNTSYSTEMSSURVELANCERUIREMENTS Continued 4.6.3.1.2Eachcontainment isolation valveshallbedemonstrated OPERABLEduringtheCOLDSHUTDOHHorREFUELING NODEatleastonceperIGmonthsby:Ia.Verifying thatonaPhaseAcontainment isolation testsignal,eachPhaseAisolation valveactuatestoitsisolation position.

b.Verifying thatonaPhaseBcontainment isolation testsignal,.eachPhaseBisolation valveactuatestoitsisolation position.

c.Verifying thatonaContainment PurgeandExhaustisolation signal,eachPurgeandExhaustvalveactuatestoitsisolation, position.

4.6.3.1.3Theisolation timeofeachpoweroperatedorautomatic containment isolation valve'shallbedetermined tobewithinitslimitwhentestedpursuanttoSpecification 4.0.5~e-pmv4~-ien~Meeh

'OOKNUCLEARPLANT-UNIT23/46-14AMENOMENT NO.97,43k458,165 COADWARRISGCOND+0ON3.6.5.9ThedividerbarriersealshallbeOPERABLE.

Withthedividerbarriersealinoperable, restorethesealtoOPERABLEstatuspriortoincreasing theReactorCoolantSystemtemperature above200'F.VECRE4.6.5.9Thedividerbarriersealshallbedetermined OPERABLEatleastonceper18monthsduringshutdownby:a.Removingtwodividerbarriersealtestcouponsandverifying thatthephysicalproperties ofthetestcouponsarewithintheacceptable rangeofvaluesshowninTable3.6-2.b.Visuallyinspecting atleast95percentoftheseal's'.entire lengthand:2.Verifying thatthesealandsealmountingboltsarepro-perlyinstalled, andVerifying thatthesealmaterialshowsnovisualevidenceofdeterioration duetoholes,ruptures, chemicalattack,abrasion, radiation damage,orchangesinphysicalappearances.

COOKNUCLEARPLANT-UNIT23/46-47AVOND~NO.M, P

LANTSYSTEMS3473COMPONENT COOLNGWAERSSTINGCONDTIO0OPERATION 3.7.3.1a.Atleasttwoindependent component coolingwaterloopsshallbeOPERABLE.

b.Atleastonecomponent coolingwaterflowpathinsupportofUnit1shutdownfunctions shallbeavailable.

Specification 3.7.3.1.b.

-AtalltimeswhenUnit1isinMODES1,2,3,or4.~CTON:WhenSpecification 3.7.3.1.a

.isapplicable'.

Withonlyonecomponent coolingwaterloopOPERABLE, restoreatleasttwoloopstoOPERABLEstatuswithin72hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WhenSpecification 3.7.P.l.b isapplicable:

3oWithnoflowpath&Unit1available, returnatleastoneflowpathtoavailable statusithin7days,orprovideequivalent shutdowncapabil'ity inUnit1andreturnatleasteflowpathtoavailable-status within-the next60days,orhave-Unit 1inHOTANDBYwithinthenext12hoursandHOTSHUTDOWNwithinthefollowing 24hours.Therequirements ofSpecification 3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.7.3.1Atleasttwocomponent coolingwaterloopsshallbedemonstrated OPERABLE:

a.Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) servicing safetyrelatedequipment thatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.

b.Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveservicing sagetyrelatedeguipment actuatestoitscorrectpositiononaSafetyInfection testsignal.gC'.byVerifying Pumtfeepm'<~Pung'~%SPCt4C.Wk~

'I,Od5.Atleastonceper18monthsduringshutdown, verifythattheunitcross-tie valvescancyclefulltravel.Following cycling,thevalveswillbeverifiedtobeintheirclosedpositions.

OKNUCLEARPLANT-UNIT23/47-12AMENDMENT NO.M,4k@,158

~~0I1

~C34.7.4ESSENTIAL SERVICEWATERSvSTEYtLIMITINGCONDITION FOROPERATION 3.7.4.1a.Aleasttwoindependent essential servicewaterloopsshallbeOP~MI>.b.Atleastoneessential servicewaterflowpathassociated withsupportofUnit1shutdownfunctions shallbeavailable.

APPLICABILITY:

Specification 3.7.4.1.a.

-MODES1,2,3,and4.Specification 3.7.4.1.b.

-AtalltimeswhenUnit1isinMODES1,2,3,or4.ACTION'hen Specification 3.7.4.1.a isapplicable:

Withonlyoneessential service~aterloopOPERABLE; restoreat.leasttwoloopsto.OPERABLEstatuswithin72hour'sorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WhenSpecification 3.7.4.l.b isapplicable:

Withnoessential servicewaterflowpathavailable insupportofUnit1shutdownfunctions, returnatleastoneflowpathtoavailable statuswithin7daysorprovideequivalent shutdowncapability inUnit1andreturntheequipment toservicewithinthenext60days,orhaveUnit1inHOTSTANDBYwithinthenext12hoursandHOTSHUTDOWNwithinthefollowing 24hours.Therequirements ofSpecification 3.0.4arenotapplicable.

SURVEILLANCE REUIRENENTS 4.7.4.1Atleasttwoessential servicewaterloopsshallbedemonstrated OPERABLE:

aeAtleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) servicing safetyrelatedequipment thatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.

b.Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveservicing safetyrelatedequipment actuatestoitscorrectpositiononaSafetyInjection testsitnalQff

~~~-~~~~caCOOKNUCL:"4Z.

PIMT-UNIT23/47-13

3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMSSURVEILLANCE REUIREMENTS Continued e.Atleastonceper18monthsby:1.Verifying thatthepressuredropacrossthecombinedHEPAfiltersandcharcoaladsorberbanksislessthan6inchesWaterGaugewhileoperating theventilation systemataflowrateof6000cfmplusorminus10%.2.a.Verifying thatonaSafetyInjection SignalfromUnit1,thesystemautomatically operatesinthepressurization/cleanup mode.&b.Verifying thatonaSafetyInjection SignalfromUnit2,thesystemautomatically operatesinthepressurization/cleanup mode.3.Verifying thatthesystemmaintains thecontrolroomatapositivepressureofgreaterthanorequalto1/16inchW.G.relativetotheoutsideatmosphere atasystemflowrateof6000cfm'plusorminus10%.Aftereachcompleteorpartialreplacement ofaHEPAfilterbankbyverifying thattheHEPAfilterbanksremovegreaterthanorequalto99%oftheDOPwhentheyaretestedin-placeinaccordance withANSIN510-1975 whileoperating theventilation systemataflowrateof6000cfmplusorminus10%.Aftereachcompleteorpartialreplacement ofacharcoaladsorberbankbyverifying thatthecharcoaladsorbers removegreaterthanorequalto99%ofahalogenated hydrocarbon refrigerant testgaswhentheyaretestedin-placeinaccordance withANSIN510-1975 whileoperating theventilation systemataflowrateof6000cfmplusorminus10%.plieable.

COOKNUCLEARPLANT-UNIT 2Page3/47-16aAMENDMENT

&,434,488,202 3/4.77SNUBBERSIHITINCCONDITION FOROPATION3.7.7.1Allsafety-related snubbersshallbeOP~~"LZ.systemsrequiredOPERABLEinthoseMODES).~CTlaPithoneormoresnubbex's inoperable, within72hoursx'eplaceorrestoretheinoperable snubber(s) toOPERABLEstatusandperformanengineering evaluation perSpecification 4.7.7.1.c onthesupported component ordeclarethesupported systeminoperable andfollowtheappropriate ACTIONstatement forthatsystem.SURVELNCREUIRNTS~C4.7.7.1Eachsnubbershallbedemonstrated OP~~LEbyperformance ofthefollowing augmented inservice inspection programandtherequirements ofSpecification 4.0.5.aVisualnsectioSnubbersarecategorized asinaccessible oraccessible duringreactoroperation.

Eachofthesecategories (inaccessible andaccessible) maybeinspected independently according tothescheduledetermined byTable3.7-9.Thevisualinspection intervalforeachtypeofsnubbershallbedetermined baseduponthecriteriaprovidedinTable3.7-9andthefirstinspection intervaldetermined usingthiscriteriashallbebaseduponthepreviousinspection intervalasestablished bytherequirements ineffectbeforeAmendment No.~.b.VisualInsectionAccetanceCriteriaVisualinspections shallverify(1)thattherearenovisibleindications ofdamageorimpairedOPERABILITY, (2)attachments tothefoundation orsupporting structure aresecure,and(3)inthoselocations wheresnubbermovementcanbemanuallyinducedwithoutdisconnecting thesnubber,thatthesnubberhasfreedomofmovementandisnotfrozenup.'Snubbers whichappearinoperable as'resultofvisualinspections shallbeclassified asunacceptable andmaybereclassified asacceptable forthepurposeofestablishing thenextvisualinspection interval,"

providing that(1)thecauseoftherejection isclearlyestablished andremediedforthatCOOKNUCLEARPLANT-UNIT23/47-20AMENDMENT NO.492,~Ž-,~159 ELECTRICAL POUTERSYSTEHSSHUTDOWNLIHITINCCONDTIQNFOROPERAION3.8.1.2Asaminimum,thefollowing A.C.electrical powersourcessnail'oeOPERABI-'ne circuitbetweentheoffsitetransmission networkandtheonsiteClass1Edistribution system,andb.Onedieselgenerator with:1.Adayfueltankcontaining amintuaunof70gallonsoffuel,2.Afuel'storagesystemcontaining aminimumindicated volumeof46,000gallonsoffuel,and3.Afueltransferpump.ACTIONPithlessthantheaboveminimumrequiredA.C.electrical power"sources

OPERABLE, suspendalloperations involving COREALTERATIONS orpositive-reactivity changes+untiltheminimumrequiredA.C.electrical powersourcesarerestoredtoOPENABLEstatus.SURVEIL'LANCE REUIEHENTS4.8.1.2TheaboverequiredA.C.electrical powersourcesshallbedemonstrated OPERABLEbytheperformance ofeachoftheSurveillance Requirements of4.8.1.1.1 and4.8.1.1.2 exceptforrequirement 4.8.1.1.2.a.5.

f*Forpurposesofthisspecification, additionofwaterfromtheRWSTdoesnotconstitute apositivereactivity additionprovidedtheboronconcentration intheRUSTisgreaterthantheminimumrequiredbySpecification 3.1.2.7.b.2.

TheCOOKNUCL:"MPLANT-UNIT23/48-9AHENDHENT NO.4M,Ma.159

~p 3/4.0LIMITINGCONDITION FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.8'LECTRICAL POWERSYSTEMSSURVEILLANCE REUIREMENTS Continued tb.Atleastonceper92daysbyverifying that:1.Thevoltageofeachconnected cellisgreaterthanorequalto2.13voltsunderfloatcharge.Thespecificgravity,corrected to/7'F,andfullelectrolyte level(fluid'tthebottomofthemaximumlevelindication mark),ofeachconnected cellisgreaterthanorequalto1.200andhasnotdecreased morethan0.03fromthevalueobservedduringtheprevioustest,and3.Theelectrolyte levelofeachconnected cellisbetweenthetopoftheminimumlevelindication markandthebottomofthemaximumlevelindication mark.Atleastonceper1&monthsbyverifying that:1.Thecells,cellplatesandbatteryracksshownovisualindication ofphysicaldamageorabnormaldeterioration, Thecell-to~ll andterminalconnections areclean,tight,freeofcorrosion andcoatedwithanti-corrosion

material, f3.Thebatterychargerwillsupplyatleast140amperesatgreaterthanorequalto250voltsforatleast4hours.Atleastonceper18months,performabatteryservicetestduringshutdown(MODES5or6),byverifying thatthebatterycapacityisadequatetosupplyandmaintaininOPERABLEstatustheactualorsimulated emergency loadsforthedesigndutycyclewhichisbasedonthecomposite loadprofile.Thecomposite loadprofileenvelopes boththeLOCA/LOOP andStationBlackoutprofilesandprovidesthebasisforthetimeslistedinTable4.8-2.Thebatterychargerwillbedisconnected throughout thetest.Thebatteryterminalvoltageshallbemaintained greaterthanorequalto210voltsthroughout thistest~Atleastonceper60months,conductaperformance testofbatterycapacityduringshutdown(MODES5or6),byverifying thatthebatterycapacityisatleast80%ofthemanufacturer's rating.Whenthistestisperformed inplaceofabatteryservicetest,amodifiedperformance testshallbeconducted.

Annualperformance testsofbatterycapacityshallbegiventoanybatterythatshowssignsofdegradation orhasreached85%oftheservicelifeexpectedfortheapplication.

Degradation isindicated whenthebatterycapacitydropsmorcthan10%fromitscapacityonthepreviousperformance test,orisbelow90%ofthemanufacturer's rating.Ifthebaueryhasreached85%ofservicelife,deliversacapacityof100%orgreaterofthemanufacturer's ratedcapacity, andhasshownnosignsofdegradation, performance testingattwoyearintervals isacceptable untilthebatteryshowssignsofdegradation.

Mte-provisions-ef-Specif catialicableCOOKNUCLEARPLANT-UNIT 2Page3/48-13AMENDME<NT 443,439,4@i,183 3/4.0LIMITINGCONDITION FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.8ELECTRICAL POWERSYSTEMSD.C.DISTRIBUTION

-SHUTDOWNLIMITINGCONDITION FOROPERATION 3.8.2.4Asaminimum,thefollowing D.C.electrical equipment andbusshallbeenergized andOPERABLE:

1-250-voltD.C.bus,and1-250-voltbatterybankandchargerassociated withtheaboveD.C.bus.APPLICABILITY:

MODES5and6.ACTION:Withlessthantheabovecomplement ofD.C.equipment andbusOPERABLE, establish CONTAINMENT INTEGRITY within8hours.SURVEILLANCE REUIREMENTS 4.8.2.4.1 Theaboverequired250-voltD.C.busshallbedetermined OPERABLEandenergized atleastonceper7daysbyverifying correctbreakeralignment andindicated poweravailability.

4.8.2.4.2 Theaboverequired250-voltbatterybankandchargershallbedemonstrated OPERABLEperSurveillance Requirement 4.8.2.3.2.~

COOKNUCLEARPLANT-UNIT 2Page3/48-15e-epplieabl

+242X2.cLfowho4-C~wtte~~+dtargcr.

ttirtnncnt AMENDMENT 443,4',183 3.9.12Thespentfuelstoragepoolexhaustventilation systemshallbeOPERABLE.

wheneverirradiated fuelisinthestoragepool.Pithnofuelstoragepoolexhaustventilation systemOPERABLE, suspendalloperations involving movementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepooluntilatleastonespentfuelstoragepoolexhaustventilation systemisrestoredtoOPERABLEstatus.*b.Theprovisions ofSpecifications 3.0.3and3.0'arenotapplicable.

S'RVVCRUITS4.9.12Theaboverequiredfuelstoragepoolventilation systemshallbedemonstrated OPERABLE:

a.Atleastonceper31daysbyinitiating flowthroughtheHEPAfilterandcharcoaladsorbertrainandverifying

-hatthetrainoperatesforatleast15minutes.b.Atleastonceper18monthsor(1)afteranystructural maintenance ontheHEPAfilterorcharcoaladsorberhousings, or(2)following

painting, fireorchemicalreleaseinanyventilation zonecommunicating withthesystem,by:1.Deleted.,C.COOK-UNIT23/49-12Amendment No1112.Verifying thatthecharcoaladsorbers remove)99%ofahalogenated hydrocarbon

-,refrigerant testgaswhentheyaretestedin-placeinaccordance withANSIN510-1980 whileoperating theexhaustventilation systemataflawrateof30,000cfm+10%.gillieQALac4%clqqrog~clvxllI+Thecranebayroll-updoorandthemaybeopenedunderadministrative control.duringmovementoffuelwithinthestoragepoolorcrane.operation withloadsoverthestoragepool.SharedsystemwithD.C.COOK-UNIT1.Thisdoesnotincludethemainloadblock.Forpurposesofthisspecification, adeenergized mainloadblockneednotbeconsidered aload.

5.0DESIGNFEATURES5.6FUELSTORAGEContinued CRITICALITY

-SPENTFUELContinued Theequivalent reactivity criteriaforRegion2andRegion3isdefinedviathefollowing equations'an~mphieai~ieted=in=Rgtt~~

ForReion2StoraeMinimumAssemblyAverageBurnupinMWD/MTU=-22,670+22,220E-2,260E+149EForReion3StoraeMinimumAssemblyAverageBurnupinMWD/MTU=-26,745+18,746E-1,631E2+98.4E3WhereE=InitialPeakEnrichment 5.6.1.2FuelstoredinthespentfuelstorageraCksshallhaveanominalfuelassemblyenrichment asfollows:Description MaximumNominalFuelAssemblyEnrichment Wt.%U-2351)Westinghouse 2)Exxon/ANF 3)Westinghouse 4)Exxon/ANF 15x15STD15x15OFA15x1517x17STD17x17OFA17x17V517x174.954.954.954.95COOKNUCLEARPLANT-UNIT 2Page54AMENDMENT 44,424,447,4',198

'3r'94~C~ZCCCruporpxi~ccBUrc%lPL"=MAN2LosI(tl~EiA~~f.4.14LOLSLOA+A44.~IN~i.BlRlCHMKHT,

%U-2355-8

6.0 ADMINISTRATIVE

CONTROLS6.3FACILITYSTAFFUALIFICATIONS 6.3.1Eachmemberofthefacilitystaffshallmeetorexceed!he minimumqualifications ofANSIN18.1-1971 forcomparable positions, exceptfor(I)thePlantRadiation Protection Manager,whoshallmeetorexceedqualifications ofRegulatory Guide1.8,September 1975,(2)theShiftTechnical Advisor,whoshallhaveabachelor's degreeorequivalent inascientific orengineering discipline withspecifictraininginplantdesign,andresponseandanalysisoftheplantfortransients andaccidents and,(3)theOperations Superintendent, whomusthetthuntmuohct

'.craterLtspecified inSection6.2.2P.6.4TRAINING6.4.1Aretraining andreplacement trainingprogramforthefacilitystaffshallbemaintained underthedirection oftheTrainingManagerandshallmeetorexceedtherequirements andrecommendations ofSection5.5ofANSIN18.1-1971 and10CFRPart55.6.5REVIEWANDAUDIT6.5.1PLANTNUCLEARSAFETYREVIEWCOMMITTEE PNSRCFUNCTION6.5.1.1ThePNSRCshallfunctiontoadvisetheSiteVicePresident/Plant Manager,ordesigne",

onallmattersrelatedtonuclearsafety.COMPOSITION 6.5.1.2ThePNSRCshallbecomposedofAssistant PlantManagers, Department Superintendents, orsupervisory personnel reporting directlytotheSiteVicePresident/Plant Manager,Assistant PlantManagersorDepartment Superintendents.

Themembership shallrepresent thefunctional areasoftheplant,including, butnotlimitedtoOperations, Tcchnical Support,Licensing, Maintenance andRadiation Protection.

ThePNSRCmembership shallconsistofatleastoneindividual fromeachoftheareasdesignated.

Allmembers,including theChairmanandhisalternates, themembersandtheiralternates, shallbedesignated bytheSiteVicePresident/Plant Manager.PNSRCmembersandalternates shallmeetorexceedtheminimumqualifications ofANSIN18.1-1971Section4.4forcomparable positions.

Thenuclearpowerplantoperations individual shallmeetthequalifications ofSection4.2.2ofANSIN18.1-1971 exceptfortherequirement toholdacurrentSeniorOperatorLicense.Theoperations individual mustholdorhaveheldaSeniorOperatorLicenseorhavebeencertified forequivalent senioropeiatorknowledge atCookNuclearPlantorasimilarreactor.Themaintenance individual shallmeetthequalifications ofSection4.2.3ofANSIN18.1-1971.

COOKNUCLEARPLANT-UNIT 2Page6-4AMENDMENT 34,447)438,4VR,47$,197

ATTACHMENT 3ATOAEP:NRC:0433Q PROPOSEDTECHNICAL SPECIFICATIONS PAGESREVISEDPAGESUNIT13/40"33/43-2la3/44-383/44-403/47-153/49-13/49-135-65-7b6-4 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.0APPLICABILITY SURVEILLANCE REQUIREMENTS Surveillance intervals specified inSectionXIoftheASMEBoilerandPressureVesselCodeandapplicable Addendafortheinservice inspection andtestingactivities requiredbytheASMEBoilerandPressureVesselCodeandapplicable Addendashallbeapplicable asfollowsintheseTechnical Specifications:

ASMEBoilerandPressureVesselCodeandapplicable Addendaterminology forinservice insctionandtestincriteriaWeeklyMonthlyQuarterly orevery3monthsSemiannually orevery6monthsYearlyorannuallyRequiredfrequencies forperforming inservice inspection andtestingactivities Atleastonceper7daysAtleastonceper31daysAtleastonceper92daysAtleastonceper184daysAtleastonceper366daysTheprovisions ofSpecification

4.0. 2areapplicable

totheaboverequiredfrequencies forperforming inservice inspection andtestingactivities.

Performance oftheabove'inservice inspection andtestingactivities shallbeinadditiontootherspecified Surveillance Requirements.

NothingintheASMEBoilerandPressureVesselCodeshallbeconstrued tosupersede therequirements ofanyTechnical Specification.

4.0.64.0.7Deleted.Deleted.COOKNUCLEARPLANT-UNIT 1Page3/40-3AMENDMENT 400,43k,444 1U~f<t 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMIi22'I'ATION ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION FUNCTIONAL UNIT6.MOTORDRIVENAUXILIARY FEEDWATER PUMPSCa.SteamGenerator Water3/Stm.Gen.Level-Low-Low 141,2,32/Stm.Gen.2/Stm.Gen.anyStm.Gen.MINIMUMTOTALNO.OFCHANNELSCHANNELSAPPLICABLE CHANNELSTOTRIPOPERABLEMODESACTIONb.4kvBusLossofVoltage3/BusPumpStartValveActuation (Bothtrains)c.SafetyInjection 2/bus(T11A-TrainB;T11D-TrainA)2/buson(T11A&T11Bor2/bussesT11C&T11D)1,2,31,2,31418'.LossofMainFeedwater Pumps7.TURBINEDRIVENAUXILIARY FEEDWATER PUMPS'21,218a.SteamGenerator Water3/Stm.Gen.Level-Low-Low b.ReactorCoolantPump4-1/BusBusUndervoltage 8.LOSSOFPOWER2/Stm.Gen.2/Stm.Gen.any2Stm.Gen.I,2,31,2,31419a.4kvBusLossofVoltage1,2,3,414b.4kvBusDegradedVoltage3/Bus(TIIA-TrainB;TIID-TrainA)2/Bus2/Bus1,2,3,4(T11A-Train B;(T11A-Train B;T11D-Train A)T11D-Train A)14COOKNUCLEARPLANT-UNIT 1Page3/43-21nAMENDMENT

$9,48$,4' I

3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMREACTORCOOLANTVENTSYSTEMREACTORVESSELHEADVENTSSURVEILLANCE REUIREMENTS 4.4.12.1BothReactorVesselheadventpathsshallbedemonstrated OPERABLEatleastoncepert8monthsby:Verifying thecommonmanualisolation valveintheReactorvesselheadventissealedintheopenposition.

CyclingeachoftheremotelyoperatedvalvesineachpaththroughatleastonecompletecycleoffulltravelfromtheControlRoomwhileinModes5or6.Verifying flowthroughbothoftheReactorVesselheadventpathsduringventingoperation, whileinModes5or6.COOKNUCLEARPLANT-UNIT 1Page3/44-38AMENDMENT 98 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4,4REACTORCOOLANTSYSTEMREACTORCOOLANTVENTSYSTEMPRESSURIZER STEAMSPACEVENTSSURVEILLANCE REUIREMENTS 4.4.12.2BothPressnrlacr steamspaceventpathsshallbedemonstrated OPERABLEatleastoncepert8monthsby:1.Verifying thecommonmanualisolation valveinthePressurizer steamspaceventissealedintheopenposition.

CyclingeachoftheremotelyoperatedvalvesineachpaththroughatleastonecompletecycleoffulltravelfromtheControlRoomwhileinModes5or6.3.Verifying flowthroughbothofthePressurizer steamspaceventpathsduringventingoperation, whileinModes5or6.COOKNUCLEARPLANT-UNIT IPage3/4440AMENDMENT 98 3/4LIMITINGCONDITIONS IOROPERATION ANDSURVEILLANCEREQUIREMENTS 3/4.7PLANTSYSTEMSPLANTSYSTEMS3/4.7.3COMPONENT COOLINGWATERSYSTEMLIMITINGCONDITION FOROPERATION 3.7.3.1APPLICABILITY:

ACTION:Atleasttwoindependent component coolingwaterloopsshallbeOPERABLE.

Atleastonecomponent coolingwaterflowpathinsupportofUnit2shutdownfunctions shallbeavailable.

Specification 3.7.3.1.a-MODES1,2,3and4.Specification3.7.3.1.b-AtalltimeswhenUnit2isinMODES1,2,3,or4.WhenSpeciiflication3.7.3.1.a isapplicable:

Withonlyonecomponent coolingwaterloopOPERABLE, restoreatleasttwoloopstoOPERABLEstatuswithin72hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WhenSpecification3.7.3.1.b isapplicable:

WithnoflowpathtoUnit2available, returnatleastoneflowpathtoavailable statuswithin7days,orprovideequivalent shutdowncapability inUnit2andreturnatleastoneflowpathtoavailable statuswithinthenext60days,orhaveUnit2inHOTSTANDBYwithinthenext12hoursandHOTSHUTDOWNwithinthefollowing 24hours.Therequirementsof Specification3.0.4 arenotapplicable.

SURVEILLANCE REUIREMENTS 4.7.3.1Atleasttwocomponent coolingwaterloopsshallbedemonstrated OPERABLE:

Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) servicing safetyrelatedequipment thatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.

Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveservicing safetyrelatedequipment actuatestoitscorrectpositiononaSafetyInjection testsignal.Byverifying pumpperformancepursuant toSpeciftcation4.0.5.

Atleastonceperidmonthsduringshutdown, byverifying thattheunitcross-tie valvescancyclefulltravel.Following cycling,thevalveswillbeverifiedtobeintheirclosedpositions.

COOK'NUCLEAR PLANT-UNIT 1Page3/47-15dhggbtDhtgbyg gttg,ggh,ddd,ddd r>0 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCEREQUIREMENTS 3/4.9REFUELING OPERATIONS BORONCONCENTRATION LIMITINGCONDITION FOROPERATION 3.9.1Withthereactorvesselheadunboltedorremoved,theboronconcentration ofallfilledportionsoftheReactorCoolantSystemandtherefueling canalshallbemaintained uniformandsufficient toensurethatthemorerestrictive ofthefollowing reactivity conditions ismet:EitheraK,of0.95orless,whichincludesa1%Ak/kconservative allowance foruncertainties, orAboronconcentration ofgreaterthanorequalto2400ppm,whLhincludesa50ppmconservative allowance foruncertainties.

APPLICABILITY:

ACTION:MODE6Withtherequirements oftheabovespecification notsatisfied, immediately suspendalloperations involving COREALTERATIONS orpositivereactivity changes"andinitiateandcontinueborationatgreaterthanorequalto10gpmof20,000ppmboricacidsolutionoritsequivalent untilK,zisreducedtolessthanorequalto0.95ortheboronconcentration isrestoredtogreaterthanorequalto2400ppm,whichever isthemorerestrictive.

Theprovisions ofSpecification3.0.3 arenotapplicable.

SURVEILLANCE REUIREMENTS 4.9.1.1Themorerestrictive oftheabovetworeactivity conditions shallbedetermined priorto:a.Removingorunbolting thereactorvesselhead,andb.Withdrawal ofanyfulllengthcontrolrodinexcessof3feetfromitsfullyinsertedposition.

4.9.1.2Theboronconcentration ofthereactorcoolantsystemandtherefueling, canalshallbedetermined bychemicalanalysisatleastonceper72hours.'Thereactorshallbemaintained inMODE6whenthereactorvesselheadisunboltedorremoved.10Forpurposesofthisspecification, additionofwaterfromtheRWSTdoesnotconstitute apositivereactivity additionprovidedtheboronconcentration intheRWSTisgreaterthantheminimumrequiredbySpecification 3.1.2.7.b.2.

COOKNUCLEARPLANT-UNIT 1Page3/49-1AMENDMENTS%

II~~IC4kAt"t'I,K 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMIPlTS 3/4.9REFUELING OPERATIONS REFUELING OPERATIONS STORAGEPOOLVENTILATION SYSTEMh*LIMITINGCONDITION FOROPERATION 3.9.12Thespentfuelstoragepoolexhaustventilation systemshallbeOPERABLE.

APPLICABILITY:

Wheneverirradiated fuelisinthestoragepool.ACTION:a.Withnofuelstoragepoolexhaustventilation systemOPERABLE, suspendalloperations involving movementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepool+untilatleastonespentfuelstoragepoolexhaustventilation systemisrestoredtoOPERABLEstatus.'h b.Theprovisions ofSpecifications 3.0.3and3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.9.12Theaboverequiredfuelstoragepoolventilation systemshallbedemonstrated OPERABLE:

Atleastonceper31daysbyinitiating fiowthroughtheHEPAfilterandcharcoaladsorbertrainandverifying thatthetrainoperatesforatleast15minutes.Atleastonceper18monthsor(1)afteranystructural maintenance ontheHEPAfilterorcharcoaladsorberhousings, or(2)following

painting, fireorchemicalreleaseinanyventilation zonecommunicating withthesystem,by:1.Deleted.2.Verifying thatthecharcoaladsorbers remove299%ofahalogenated hydrocarbon refrigerant testgaswhentheyaretestedin-placeinaccordance withANSIN510-1980 whileoperating theexhaustventilation systemataflowrateof30,000cfmk10%.srthecranebayroti-updoorandthesouthdooroytheauxiliary buildingcranebaymaybeopenedunderadministrative controlduringmovementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepool.'pd'Shared systemwithD.C.COOK-UNIT2.+Thisdoesnotincludethemainloadblock.Forpurposesofthisspecification, adewnergized mainloadblockneednotbeconsidered aload.COOKNUCLEARPLANT-UNIT 1Page3/49-13 u'tllI'I'ras~>>'+'.,>>.r 5.0DESIGNFEATURES5.6FUELSTORAGEContinued 1.Region1isdesignedtoaccommodate newfuelwithamaximumnominalenrichment of4.95wt%U-235,orspentfuelregardless ofthedischarge fuelburnup.Region2isdesignedtoaccommodate fuelof4.95%initialnominalenrichment burnedtoatleast50,000MWD/MtU,orfuelofotherenrichments withequivalent reactivity.

Region3isdesignedtoaccommodate fuelof4.95%initialnominalenrichment burnedtoatleast38,000MWD/MtU,orfuelofotherenrichments withequivalent reactivity.

Theequivalent reacdvtqr criteriaforRegion2andRegion3isdefinedviathefollowing equations:

ForReion2Stora eMinimumAssemblyAverageBurnupinMWD/MTU=22670+22220E-2260'+149EForReion3StoraeMinimumAssemblyAverageBurnupinMWD/MTU=-26,745+18,746E-1,631E~+98.4E3WhereE=InitialPeakEnrichment 5.6.1.2:IFuelstoredinthespentfuelstorageracksshallhaveamaximumnominalfuelassemblyenrichment asfollows:MaximumNominalFuelDescription AssemblyEnrichment Wt.%U-2351)Westinghouse 2)Exxon/ANF 3)Westinghouse 4)Exxon/ANF 15x15STD15x15OFA15x1517x17STD17x17OFA17x17VS17x174.954.954.954.95COOKNUCLEARPLANT-UNIT 1Page54AMENDMENT 5V,486,448,469,SH t~'~~~I'~<<')i~4vl(Lh4'4IIIl,qyg Figure5.6-3intentionally deleted.COOKNUCLEARPLANT-UNlT 1Page5-7bAMENDMENT Bi9.

6.0 ADMINISTRATIVE

CONTROLS6.3FACILITYSTAFFUALIFICATIONS 6.3.1Eachmemberofthefacilitystaffshallmeetorexceedtheminimumqualifications ofANSIN18.1-1971 forcomparable positions, exceptfor(1)thePlantRadiation Protection Manager,whoshallmeetorexceedqualifications ofRegulatory Guide1.8,September 1975,(2)theShiftTechnical Advisor,whoshallhaveabachelor's degreeorequivalent inascientific orengineering discipline withspecifictraininginplantdesign,andresponseandanalysisoftheplantfortransients andaccidents and,(3)theOperations Superintendent, whomustbequalified asspecified inSection6.2.2.g.6.4TRAINING6.4.1Aretraining andreplacement trainingprogramforthefacilitystaffshallbemaintained underthedirection oftheTrainingManagerandshallmeetorexceedtherequirements andrecommendations ofSection5.5ofANSIN18.1-1971and10CFRPart55.6.5REVIEWANDAUDIT6.5.1PLANTNUCLEARSAFETYREVIEWCOMMITI'EE NSRCFUNCTION6.5.1.1ThePNSRCshallfunctiontoadvisetheSiteVicePresident/Plant Manager,ordesignee, onallmattersrelatedtonuclearsafety.COMPOSITION 6.5.1.2ThePNSRCshallbecomposedofAssistant PlantManagers, Department Superintendents, orsupervisory personnel reporting directlytotheSiteVicePresident/Plant Manager,Assistant PlantManagersorDepartment Superintendents.

Themembership shallrepresent thefunctional areasoftheplant,including, butnotlimitedtoOperations, Tcchnical Support,Licensing, Maintenance andRadiation Protection.

ThePNSRCmembership shallconsistofatleastoneindividual fromeachoftheareasdesignated.

Allmembers,including theChairmanandhisalternates, themembersandtheiralternates, shallbedesignated bytheSiteVicePresident/Plant Manager.PNSRCmembersandalternates shallmeetorexceedtheminimumqualifications ofANSIN18.1-1971 Section4.4forcomparable positions.

Thenuclearpowerplantoperations individual shallmeetthequalifications ofSection4.2.2ofANSIN18.1-1971 exceptfortherequirement toholdacurrentSeniorOperatorLicense.Theoperations individual mustholdorhaveheldaSeniorOperatorLicenseorhavebeencertified forequivalent senioroperatorknowledge.

atCookNuclearPlantorasimilarreactor.Themaintenance individual shallmeetthequalifications ofSection4.2.3ofANSIN18.1-1971.

COOKNUCLEARPLANT-UNIT 1Page64AMENDMENT 49,6S,4',484)486,493,212

ATTACHMENT 3BTOAEP:NRC:0433Q PROPOSEDTECHNICAL SPECIFICATIONS PAGESREVISEDPAGESUNIT2,3/40-33/40-43/43-113/43-203/43-303/43-313/43-343/43-44d3/43-473/44-133/44-143/44-333/44-353/4,4-373/45-43/45"83/46-123/46-143/46-473/47-123/47-133/47-16a3/47-203/48-93/48-133/48-153/49-125-65-86-4 3/4LIMITINGCONDITIONS FOROPERATION ANDSIRVEILLANCE REQUIREMENTS 3/4.0APPLICABILITY SURVEILLANCE REUIREMENTS b.Surveillance Intervals specified inSectionXIoftheASMEBoilerandPressureVesselCodeandapplicable Addendafortheinservice inspection andtestingactivities requiredbytheASMEBoilerandPressureVesselCodeandapplicable Addendashallbeapplicable asfollowsintheseTechnical Specifications:

ASMEBoilerandPressureVesselCodeandapplicable Addendaterminology forinservice inspection andtestingcriteriaWeeklyMonthlyQuarterly orevery3monthsSemiannually orevery6monothsYearlyorannuallyRequiredfrequencies forperforming inservice inspection andtestingactivities Atleastonceper7daysAtleastonceper31daysAtleastonceper92daysAtleastonceper184daysAtleastonceper366daysc.Theprovisions ofSpecification

4.0. 2areapplicable

totheaboverequiredfrequencies forperforming inservice inspection andtestingactivities.

Performance oftheaboveinservice inspection andtestingactivities shallbeinadditiontootherspecified Surveillance Requirements.

NothingintheASMEBoilerandPressureVesselCodeshallbeconstrued tosupersede therequirements ofanyTechnical Specification.

4.0.6Deleted.4.0.7Deleted.COOKNUCLEARPLANT-UNIT 2Page3/40-3AMENDMENT VS,QV,48k 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCEREQUIREMENTS 3/4.0APPLICABILITY SURVEILLANCE REUIREMENTS 4.0.8Deleted.4.0.9Deleted.COOKNUCLEARPLANT-UNIT2 1Page3/4S4~wuMHmm,m TABLE4.3-1REACTORTRIPSYSTEMINSTRUMENTATION SURVEILLANCE REUIREMENTS FUNCTIONAL UNIT1.ManualReactorTripA.ShuntTripFunctionB.Undervoltage TripFunction2.PowerRange,NeutronFlux3.PowerRange,NeutronFlux,HighPositiveRate4.PowerRange,NeutronFlux,HighNegativeRate5.Intermediate Range,NeutronFlux6.SourceRange,NeutronFlux7.Overtemperature b,T8.Overpower hT9.Pressurizer Pressure-Low10.Pressurizer Pressure-High11.Pressurizer WaterLevel-High12.LossofFlow-Single LoopCHANNELCHECKN.A.N.A.SN.A.CHANNELCALIBRATION N.A.N.A.D(2,8),M(3,8)andQ(6,8)R(6)R(6)R(6,8)R(6,14)R(9)R(9)R(8)CHANNELFUNCTIONAL TESTS/U(1)(10)

S/U(1)(10)

MandS/U(1)S/U(1)M(14)GildS/U(1)MMMODEINWHICHSURVEILLANCE REUIREDI,2,3,4,51,2,3,4',51,2and1,21,21,2,and2(7),3(7),4and51,21,21,21,21,2 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE3.3-3Continued ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION FUNCTIONAL UNIT7.TURBINEDRIVENAUXILIARY FEEDWATER PUMPSMINIMUMTOTALNO.CHANNELSCHANNELSOFCHANNELSTOTRIPOPERABLEAPPLICABLE MODESACTIONa.SteamGenerator Water3/Stm.Gen.Level-Low-Low2/Stm.Gen.2/Stm.Gen.any2Stm.Gen.1,2,314'.ReactorCoolantPump4-1/BusBusUndervoltage 8.LOSSOF'POWER1,2,319'.4kVBusLossofVoltageb.4kVBusDegradedVoltage9.MANUALa.SafetyInjection (ECCS)Feedwater Isolation ReactorTrip(SI)Containment Isolation-Phase"A"Containment PurgeandExhaustIsolation Auxiliary Feedwater PumpsEssential ServiceWaterSystemb.Containment SprayContainment Isolation-Phase"B"Containment PurgeandExhaustIsolation Containment AirRecirculation Fanc.Containment Isolation-Phase"A"Containment PurgeandExhaustIsolation d.SteamLineIsolation 3/Bus3/BusP21A-Train8;T21D-TninA)2/train1/train1/train2/steamline(1pertrain)2/Bus(T21A-Tnin8;TZID-Train A)1/train1/train1/train2/steamline(1pertrain)2/Bus2/Bus(TRIA-Tnin B;T21D-Tnin A)2/train1/train1/train2/operating steamline(1pertrain)1,2,3,414',2,3,4 141,2,3,4181,2,3,4181,2,3,4181,2,320COOKNUCLEARPLANT-UNIT 2Page3/43-20AMENDMENT VV;4%,437 3/4LIMlTINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE4.3-2ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION SURVEILLANCE REUIREMENTS FUNCFIONAL UNITl.SAFETYINJECTION, TURBINETRIP,FEEDWATER ISOLATION, ANDMOTORDRIVENAUXILIARY FEEDWATER PUMPSTRIPACTUATING DEVICEOPERATIONAL MODESINCHANNELWHICHCHANNELCHANNELFUNCTIONAL SURVEILLANCE CHECKCALIBRATION TEST~RE(EUIRED a.ManualInitiation b.Automatic Actuation Logicc.Containment Pressure-Highd.Pressurizer Pressure-Lowe.Differential PressureBetweenSteamLines-Highf.SteamLincPressure-LowN.A.M(3)N.A.N.A.N.A.N.A.SecFunctional Unit9M(2)N.A.I,2,3,4I,2,3I,2,3I,2,3I,2,32.CONTAINMENT SPRAYa.ManualInitiation b.Automatic Actuation Logicc.Containment Pressurc-High-High 3.CONTAINMENT ISOLATION a.PhaseAIsolation I)Manual2)FromSafetyInjection Automatic Actuation Logicb.PhaseBIsolation I)Manual2)Automatic Actuation Logic3)Containment Pressure-High-HighN.A.N.A.N.A.N.A.N.A.SeeFunctional Unit9M(2)M(3)SecFunctional Unit9M(2)SeeFunctional Unit9M(2)M(3)N.A.N.A.N.A.N.A.N.A.I,2,3,4I,2,3I,2,3,4I,2,3,4I,2,3COOKNUCLEARPLANT-UNlT 2Page3/43-30AMENDMENT 84,9,43V,488 g~tb0II 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE4.3-2Continued ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION SURVEILLANCE REUIREMENTS FUNCTIONAL UNITc.PurgeandExhaustIsolation CHANNELCHECKCHANNELCALIBRATION CHANNELFUNCfIONAL TESTTRIPACTUATING DEVICEOPERATIONAL MODESINWHICHSURVEILLANCE RHtHUIRED I)Manual2)Containment Radioactivity

-HighSeeFunctional Unit9eN.A.I,2,3,44.STEAMLINEISOLATION a.Manualb.Automatic Actuation Logicc.Containment Pressure-High-High d.SteamHowinTwoSteamLines-HighCoincident withT~-Low-Lowc.SteamLinePressure-LowN.A.N.A.SeeFunctional Unit9M(2)M(3)MN.A.N.A.N.A.N.A.I,2,31,2,31,2,31,2,35.TURBINETRIPANDFEEDWATER ISOLATION a.SteamGenerator WaterLcvcl-High-High MN.A.1,2,36.MOTORDRIVENAUXILIARY FEEDWATER PUMPSa.SteamGenerator WaterLevel-Low-Lowb.4kVBusLossofVoltageSc.SafetyInjection N.A.d.LossofMainFeedPumpsN.A.RN.A.N.A.MM(2)RN.A.N.A.N.A.N.A.1,2,31,2,3I,2,31,2COOKNUCLEARPLANT-UNIT2 Page3/43-31AMENDMENT%,

%,43k,434,4&V,

~)~/,~

3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4,3INFIRUMENTATION INSTRUMENTATION 3/4.3.3MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITINGCONDITION FOROPERATION 3.3.3.1Theradiation monitoring instrumentation channelsshowninTable3.3-6shallbeOPERABLEwiththeiralarm/trip setpoints withinthespecified limits.APPLICABILITY:

ACTION:AsshowninTable3.3-6.b.Witharadiation monitoring channelalarm/trip setpointexceeding thevalueshowninTable3.3-6,adjustthesetpointtowithinthelimitwithin4hoursordeclarethechannelinoperable.

Withoneormoreradiation monitoring channelsinoperable, taketheACTIONshowninTable3.3-6.c.Theprovisions ofSpecifications 3.0.3and3.0.4arenotapplicable SURVEILLANCE REUIREMENTS 4.3.3.1Eachradiation monitoring instrumentation channelshallbedemonstrated OPERABLEbytheperformance oftheCHANNELCHECK,CHANNELCALIBRATION andCHANNELFUNCTIONAL TESToperations duringthemodesandatthefrequencies showninTable4.3-3.COOKNUCLEARPLANT-UNIT 2Page3/43-34 TABLE4.3-6AAPPENDIXRREMOTESHUTDOWNMONITORING INSTRUMENTATION SURVEILLANCE REUIREMENTS 00RCORIRtA4JC4INSTRUMENT 1.SteamGenerators 1and4Level2.SteamGenerators 2and3Level3.SteamGenerators 1and4Pressure4.SteamGenerators 2and3Pressure5.ReactorCoolantLoop4Temperature (Cold)6.ReactorCoolantLoop4Temperature (Hot)7.ReactorCoolantLoop2Temperature (Cold)ReactorCoolantLoop2Temperature (Hot)9.Pressurizer Level10.ReactorCoolantSystemPressure11.ChargingCross-Flow BetweenUnits12.SourceRangeNeutronDetector(N-23)LOCATIONLSICabinet1andLSICabinet4LSICabinet2andLSICabinet4LSICabinet4andLSICabinet5LSICabinet4andLSICabinet6LSICabinet4andLSICabinet5LSICabinet4andLSICabinet5LSICabinet4andLSICabinet6LSICabinet4andLSICabinet6,LSICabinet3LSICabinet3CorridorElev.587'SICabinet4CHANNELCHECKMCHANNELCALIBRATION

,R*Charging Cross-Flow betweenUnitsisaninstrument commontobothUnitIand2.Thissurveillance willonlybeconducted onanintervalconsistent withUnitIrefueling.

TABLE4.3-10POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REUIREMENTS INSTRUMENT CHANNELCHECKCHANNELCALIBRATION 1.2.3.4.5.6.7.8.9.10.11.12.13.14.15.16.17.18.Containment PressureReactorCoolantOutletTemperature

-Tnor(WideRange)ReactorCoolantInletTemperature

-Tco~(WideRange)ReactorCoolantPressure-WideRangePressurizer WaterLevelSteamLinePressureSteamGenerator WaterLevel-NarrowRangeRWSTWaterLevelBoricAcidTankSolutionLevelAuxiliary Feedwater FlowRateReactorCoolantSystemSubcooling MarginMonitorPORVPositionIndicator

-LimitSwitchesPORVBlockValvePositionIndicator

-LimitSwitchesSafetyValvePositionIndicator

-AcousticMonitorIncoreThermocouples (CoreExitThermocouples)

ReactorCoolantInventory TrackingSystem(ReactorVesselLevelIndication)

Containment SumpLevelContainment WaterLevelMMMMMMMMMMMMMMMMu~MMRRRRRRRRRRRRRRRtuRP)RRtnPartial rangechannelcalibration forsensortobeperformed belowP-12inMODE3."KithonetrainofReactorVesselLevelIndication inoperable, Subcooling MarginIndication andCoreExitThermocouples maybeusedtoperformaCHANNELCHECKtoverifytheremaining ReactorVesselIndication trainOPERABLE.

+Completion ofchannelcalibration forsensorstobeperformed belowP-12inMODE3.

-001STSAMPLEINSPECTION TABLE4.4-2STEAMGENERATOR TUBEINSPECTION 2NDSAMPLEINSPECTION 3RDSAMPLEINSPECTION SampleSizeAminimumofSTubesperS.G.ResultC-1C-2ActionRequiredNonePlugdefective tubesandinspectadditional 2StubesinthisS.G.ResultN/AC-1C-2ActionRequiredN/ANonePlugdefective tubesandinspectadditional 4StubesinthisS.G.ResultN/AN/AC-1ActionRequiredN/AN/ANoneC-3InspectalltubesinthisS.G.,plugdefective tubesandinspect2StubesineachotherS.G.C-3AllotherS.G.sareC1PerformactionforC-3resultoffirstsampleNoneC-2C-3N/AN/APlugdefective tubesPerformactionforC-3resultoffirstsampleN/AN/APromptnotification toNRCpursuanttospecification 6.9.1SomeS.G.sPerformactionforC-2C-2butnoresultofsecondsampleadditional S.G.areC-3.N/AN/AAdditional S.G.isC-3InspectalltubesineachS.G.andplugdefective tubes.Promptnotification toNRCpursuanttospecification 6.9.1.'/AN/AS=3(N+n)%

WhereNisthenumberofsteamgenerators intheunit,andnisthenumberofsteamgenerators inspected duringaninspection.

IIh 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEM3/4.4.6REACTORCOOLANTSYSTEMLEAKAGELEAKAGEDETECTION SYSTEMSLIMITINGCONDITION FOROPERATION 3.4.6.1Thefollowing ReactorCoolantSystemleakagedetection systemsshallbeOPERABLE:

a1APPLICABILITY:

Oneofthecontainment atmosphere particulate radioactivity monitoring channels(ERS-2301orERS-2401),

Thecontainment sumplevelandflowmonitoring system,andEitherthecontainment humiditymonitororoneofthecontainment atmosphere gaseousradioactivity monitoring channels(ERS-2305 orERS-2405).

MODES1,2,3and4ACTION:Withonlytwooftheaboverequiredleakagedetection systemsOPERABLE, operation maycontinueforupto30daysprovidedgrabsamplesofthecontainment atmosphere areobtainedandanalyzedatleastonceper24hourswhentherequiredgaseousand/orparticulate radioactivity monitoring channelsareinoperable; otherwise, beinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.SURVEILLANCE REUIREMENTS 4.4.6.1Theleakagedetection systemsshallbedemonstrated OPERABLEby:Containment atmosphere particulate andgaseous(ifbeingused)monitoring system-performance ofCHANNELCHECK,CHANNELCALIBRATION andCHANNELFUNCTIONAL TESTatthefrequencies specified inTable4.3-3.Containment sumplevelandflowmonitoring system-perfo'rmance ofCHANNELCALIBRATION atleastonceper18months.C.Containment humiditymonitor(ifbeingused)-performance ofCHANNELCALIBRATION atleastonceper18months.COOKNUCLEARPLANT-UNIT 2Page3/44-14AMENDMENT V8,43k,459 II1>i~C5PI 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMREACTORCOOLANTSYSTEMLIMITINGCONDITION FOROPERATION Continued WithPORVsandblockvalvesnotinthesamelineinoperable duetocausesotherthanexcessive seatleakage,within1hourrestorethevalvestoOPERABLEstatusorcloseandde-energize theassociated blockvalveandplacetheassociated PORVinmanualcontrolineachrespective line.ApplytheportionsofACTIONcordabove,relatingtotheOPERATIONAL MODE,asappropriate fortwoorthreelinesunavailable.

h.Theprovisions ofSpecification 3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.4.1F1Inadditiontotherequirements ofSpecification 4.0.5,eachPORVshallbedemonstrated OPERABLE:

a.Atleastonceper31daysbyperformance ofaCHANNELFUNCTIONAL TEST,excluding valveoperation, andb.Atleastonceper18monthsbyoperating thePORVthroughonecompletecycleoffulltravelduringMODES3or4,andc.Atleastonceper18monthsbyoperating solenoidaircontrolvalvesandcheckvalvesinPORVcontrolsystemsthroughonecompletecycleoffulltravel,andd.Atleastonceper18monthsbyperforming aCHANNELCALIBRATION oftheactuation instrumentation.

4.4.11.2Eachblockvalveshallbedemonstrated OPERABLEatleastonceper92daysbyoperating thevalvethroughonecompletecycleoffulltravelunlesstheblockvalveisclosedinordertomeettherequirements ofACTIONb,c,ordinSpecification 3.4.11.4.4.11.3Deleted.COOKNUCLEARPLANT-UNIT 2Page3/44-33AMENDMENT 45k)458,459,46k,496

~~w8'IllI00,t~+il~p"/'qI'r',ii'I'9 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMREACTORCOOLANTVENTSYSTEM"'EACTORVESSELHEADVENTSSURVEILLANCE REUIREMENTS 4.4.12.1BothReactorVesselheadventpathsshallbedemonstrated OPERABLEatleastonceper18monthsby:Verifying thecommonmanualisolation valveintheReactorvesselheadventissealedintheopenposition.

CyclingeachoftheremotelyoperatedvalvesineachpaththroughatleastonecompletecycleoffulltravelfromtheControlRoomwhileinModes5or6.Verifying flowthroughbothoftheReactorVesselheadventpathsduringventingoperation, whileinModes5or6.COOKNUCLEARPLANT-UNIT 2Page3/44-35AMENDMENT 65

3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMREACTORCOOLANTVENTSYSTEMPRESSURIZER STEAMSPACEVENTSSURVEILLANCE REUIREMENTS 4.4.12.2BothPressurizer steamspaceventpathsshallbedemonstrated OPERABLEatleastonceper18monthsby:1.Verifying thecommonmanualisolation valveinthePressurizer steamspaceventissealedintheopenposition.

2.CyclingeachoftheremotelyoperatedvalvesineachpaththroughatleastonecompletecycleoffulltravelfromtheControlRoomwhileinModes5or6.3.Verifying flowthroughbothofthePressurizer steamspaceventpathsduringventingoperation, whileinModes5or6.COOKNUCLEARPLANT-UNIT 2Page3/44-37AMENDMHNT dd

~')F+F~<<g/<<I,F<<b~<<"<<,"P<<FY 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4,5EMERGENCY CORECOOLINGSYSTEMS(ECCS)SURVEILLANCE REUIREMENTS 4.5.2EachECCSsubsystem shallbedemonstrated OPERABLE:

aoAtleastonceper12hoursbyverifying thatthefollowing valvesareintheindicated positions withpowertothevalveoperators removed:ValveNumberValveFunctionValvePositiona.IM0-390b.IMO-315c.IM0-325d.IM0-262'.

IM0-263f.~IM0-261'.

ICM-305'l.

ICM-306'.

RWSTtoRHRb.LowheadSItoHotLegc.LowheadSItoHotLegd.Miniflowlinee.Miniflowlinef.SISuctiong.SumpLineh.SumpLinea.Openb.Closedc.Closedd.Opene.Openf.Openg.Closedh.Closedb.Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) intheflowpaththatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.

c.Byavisualinspection whichverifiesthatnoloosedebris(rags,trash,clothing, etc.)ispresentinthecontainment whichcouldbetransported tothecontainment sumpandcauserestriction ofthepumpsuctionsduringLOCAconditions.

Thisvisualinspection shallbeperformed:

1.Forallaccessible areasofthecontainment priortoestablishing CONTAINMENT INTEGRITY, and2.Oftheareasaffectedwithincontainment atthecompletion ofeachcontainment entrywhenCONTAINMENT INTEGRITY isestablished.

Thesevalvesmustchangepositionduringtheswitchover frominjection torecirculation fiowfollowing LOCA.COOKNUCLEARPLANT-UNIT 2Page3/454~mnmmvs,m

'tAU"~av',>I'~~

3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.5EMERGENCY CORECOOLINGSYSTEMS(ECCS)SURVEILLANCE REUIREMENTS 4.5.3.1,TheECCSsubsystem shallbedemonstrated OPERABLEpertheapplicable Surveillance

!Requirements of4.5.2.4.5.3.2Allchargingpumpsandsafetyinjection pumps,excepttheaboverequiredOPERABLEchargingpump,shallbedemonstrated inoperable, byverifying thatthemotorcircuitbreakershavebeenremovedfromtheirelectrical powersupplycircuits, atleastonceper12hourswheneverthetemperature ofoneormoreoftheRCScoldlegsislessthanorequalto15ZFasdetermined atleastonceperhourwhenanyRCScoldlegtemperature isbetween15ZFand200'F.COOKNUCLEARPLANT-UNIT 2Page3/454

.wa 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.6CONTAINMENT SYSTEMSSURVEILLANCE REUIREMENTS Continued Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveintheflowpathactuatestoitscorrectpositiononaContainment Pressure-High-High testsignal.Atleastonceper5yearsbyverifying awaterflowrateofatleast20gpm(greaterthanorequalto20gpm)butnottoexceed50gpm(lessthanorequalto50gpm)fromthesprayadditivetanktestlinetoeachcontainment spraysystemwiththespraypumpoperating onrecirculation withapumpdischarge pressuregreaterthanorequalto255psig.COOKNUCLEARPLANT-UNIT 2Page3/46-12 p~a(~sII*V~~fC 3/4LIMrIINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.6CONTAINMENT SYSTEMSSURVEILLANCE REUIREMENTS Continued 4.6.3.1.2 Eachcontainment isolation valvespecified shallhcdemonstrated OPERABLEduringtheCOLDSHUTDOWNorREFUELING MODEatleastonceper18monthsby:Verifying thatonaPhaseAcontainment isolation testsignal,eachPhaseAisolation valveactuatestoitsisolation position.

Verifying thatonaPhaseBcontainment isolation testsignal,eachPhaseBisolation valveactuatestoitsisolation position.

Verifying thatonaContainment PurgeandExhaustisolation signal,eachPurgeandExhaustvalveactuatestoitsisolation position.

4.6.3.1.3 Theisolation timeofeachpoweroperatedorautomatic containment isolation valveshallbedetermined tobewithinitslimitwhentestedpursuanttoSpecification 4.0.5.COOKNUCLEARPLANT-UNIT 2Page3/46-14AMENDMENT PP,age,Sgg,Sdg e~4gIfII'veg~CjJf~gIt'IIf~~0'lli'JfII,Ifll1J 3/4LIMH'INGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.6CONTAINMENT SYSTEMSDIVIDERBARRIERSEALLIMITINGCONDITION FOROPERATION 3.6.5.9ThedividerbarriersealshallbeOPERABLE.

APPLICABILITY:

MODES1,2,3and4.ACTION:Withthedividerbarriersealinoperable, restorethesealtoOPERABLEstatuspriortoincreasing theReactorCoolantSystemtemperature above200'F.SURVEILLANCE REUIREMENTS 4.6.5.9Thedividerbarriersealshallbedetermined OPERABLEatleastonceper18monthsduringshutdownby:Removingtwodividerbarriersealtestcouponsandverifying thatthephysicalproperties ofthetestcouponsarewithintheacceptable rangeofvaluesshowninTable3.6-2.Visuallyinspecting atleast95percentoftheseal'sentirelengthand:Verifying thatthesealandsealmountingboltsareproperlyinstalled, andVerifying thatthesealmaterialshowsnovisualevidenceofdeterioration duetoholes,ruptures, chemicalattack,abrasion, radiation damage,orchangesinphysicalappearances.

COOKNUCLEARPLANT-UNIT 2Page3/46-47AMENDMENT V8,4R,459 lltil>t~Hyi'~I,gp)I.AlIs~r1"i<<e' 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMSi3/4.7.3COMPONENT COOLINGWATERSYSTEMLIMITINGCONDITION FOROPERATION 3.7.3.1alAtleasttwoindependent component coolingwaterloopsshallbeOPERABLE.

Atleastonecomponent coolingwaterflowpathinsupportofUnit1shutdownfunctions shallbeavailable.

APPLICABILITY:

ACTION:Specification 3.7.3.1.a.

-MODES1,2,3,4.Specification 3.7.3.1.b.

-AtalltimeswhenUnit1isinMODES1,2,3,or4.WhenSpecification 3.7.3.1.a isapplicable:

Withonlyonecomponent coolingwaterloopOPERABLE, restoreatleasttwoloopstoOPERABLEstatuswithin72hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WhenSpecification 3.7.3.1.b isapplicable:

WithnoflowpathtoUnit1available, returnatleastoneflowpathtoavailable statuswithin7days,orprovideIequivalent shutdowncapability inUnit1andreturnatleastoneflowpathtoavailable statuswithinthenext60days,orhaveUnit1inHOTSTANDBYwithinthenext12hoursandHOTSHUTDOWNwithinthefollowing 24hours.Therequirements ofSpecification 3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.7.3.1Atleasttwocomponent coolingwaterloopsshallbedemonstrated OPERABLE:

Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) servicing safetyrelatedequipment thatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.

b.Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveservicing safetyrelatedequipment actuatestoitscorrectpositiononaSafetyInjection testsignal.Ic.Byverifying pumpperformance pursuanttoSpecification 4.0.5.d.Atleastonceper18monthsduringshutdown, verifythattheunitcross-tie valvescancyclefulltravel.Following cycling,thevalveswillbeverifiedtobeintheirclosedpositions.

COOKNUCLEARPLANT-UNIT 2Page3/47-12AMENDMENT

%,44G,43k,458

~~'~,4'jt(~'g 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMS3/4.7.4ESSENTIAL SERVICEWATERSYSTEMLIMITINGCONDITION FOROPERATION 3.7.4.1a.Atleasttwoindependent essential servicewaterloopsshallbeOPERABLE.

b.Atleastoneessential servicewaterflowpathassociated withsupportofUnit1shutdownfunctions shallbeavailable.

APPLICABILITY:

Specification 3.7.4.1.a.

-MODES1,2,3,and4.Specification 3.7.4.1.b.

-AtalltimeswhenUnit1isinMODES1,2,3,or4.ACTION:WhenSpecification 3.7.4.1.a isapplicable:

Withonlyoneessential servicewaterloopOPERABLE, restoreatleasttwoloopstoOPERABLEstatuswithin72hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WhenSpecification 3.7.4.1.b isapplicable:

Withnoessential servicewaterflowpathavailable insupportofUnit1shutdownfunctions, returnatleastonefiowpathtoavailable statuswithin7daysorprovideequivalent shutdowncapability inUnit1andreturntheequipment toservicewithinthenext60days,orhaveUnit1inHOTSTANDBYwithinthenext12hoursandHOTSHUTDOWNwithinthefollowing 24hours.Therequirements ofSpecification 3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.7.4.1Atleasttwoessential servicewaterloopsshallbedemonstrated OPERABLE:

Atleastonceper31daysbyverifying thateachvalve(manual,poweroperatedorautomatic) servicing safetyrelatedequipment thatisnotlocked,sealed,orotherwise securedinposition, isinitscorrectposition.

Atleastonceper18monthsduringshutdown, byverifying thateachautomatic valveservicing safetyrelatedequipment actuatestoitscorrectpositiononaSafetyInjection testsignal.COOKNUCLEARPLANT-UNIT 2Page3/47-13AMENDMENT

%,446,48k,458,459

~tHC/nH 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMSSURVEILLANCE REUIREMENTS Continued e.Atleastonceper18monthsby:1.Verifying thatthepressuredropacrossthecombinedHEPAfiltersandcharcoaladsorberbanksislessthan6inchesWaterGaugewhileoperating theventilation systemataflowrateof6000cfmplusorminus10%.2.a.Verifying thatonaSafetyInjection SignalfromUnit1,thesystemautomatically operatesinthepressurization/cleanup mode.b.Verifying thatonaSafetyInjection SignalfromUnit2,thesystemautomatically operatesinthepressurization/cleanup mode.3.Verifying thatthesystemmaintains thecontrolroomatapositivepressureofgreaterthanorequalto1/16inchW.G.relativetotheoutsideatmosphere atasystemflowrateof6000cfmplusorminus10%.Aftereachcompleteorpartialreplacement ofaHEPAfilterbankbyverifying thattheHEPAfilterbanksremovegreaterthanorequalto99%oftheDOPwhentheyaretestedin-placeinaccordance withANSIN510-1975 whileoperating theventilation systemataflowrateof6000cfmplusorminus10%.iAftereachcompleteorpartialreplacement ofacharcoaladsorberbankbyverifying thatthecharcoaladsorbers removegreaterthanorequalto99%ofahalogenated hydrocarbon refrigerant testgaswhentheyaretestedin-placeinaccordance withANSIN510-1975 whileoperating theventilation systemataflowrateof6000cfmplusorminus10%.COOKNUCLEARPLANT-UNIT 2Page3/47-16aAMENDMENT W,m,m,am os~dk'l>>g46~0I'eri" 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMS3/4.7.7SNUBBERSLIMITINGCONDITION FOROPERATION 3.7.7.1Allsafety-related snubbersshallbeOPERABLE.

APPLICABILITY:

MODES1,2,3and4.(MODES5and6forsnubberslocatedonsystemsrequiredOPERABLEinthoseMODES).ACTION:Withoneormoresnubbersinoperable, within72hoursreplaceorrestoretheinoperable snubber(s) toOPERABLEstatusandperformanengineering evaluation perSpecification 4.7.7.1.c onthesupported component ordeclarethesupported systeminoperable andfollowtheappropriate ACTIONstatement forthatsystem.SURVEILLANCE REUIREMENTS 4.7.7.1Eachsnubbershallbedemonstrated OPERABLEbyperformance ofthefollowing augmented inservice inspection programandtherequirements ofSpecification 4.0.5.VisualInsctionSnubbersarecategorized asinaccessible oraccessible duringreactoroperation.

Eachofthesecategories (inaccessible andaccessible) maybeinspected independently according tothescheduledetermined byTable3.7-9.Thevisualinspection intervalforeachtypeofsnubbershallbedetermined baseduponthecriteriaprovidedinTable3.7-9andthefirstinspection intervaldetermined usingthiscriteriashallbebaseduponthepreviousinspection intervalasestablished bytherequirements ineffectbeforeAmendment No.156.VisualInsctionAccetanceCriteriaVisualinspections shallverify(1)thattherearenovisibleindications ofdamageorimpairedOPERABILITY, (2)attachments tothefoundation orsupporting structure aresecure,and(3)inthoselocations wheresnubbermovementcanbemanuallyinducedwithoutdisconnecting thesnubber,thatthesnubberhasfreedomofmovementandisnotfrozenup.Snubberswhichappearinoperable asaresultofvisualinspections shallbeclassified asunacceptable andmaybereclassified asacceptable forthepurposeofestablishing thenextvisualinspection

interval, providing that(1)thecauseoftherejection isclearlyestablished andremediedforthatCOOKNUCLEARPLANT-UNIT 2Page3/47-20AMENDMENT ue,m,1,m rrIAh,l,a 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.8ELECTRICAL POWERSYSTEMSELECTRICAL POWERSYSTEMSSHUTDOWNLIMITINGCONDITION FOROPERATION 3.8.1.2Asaminimum,thefollowing A.C.electrical powersourcesshallbeOPERABLE:

Onecircuitbetweentheoffsitetransmission networkandtheonsiteClass1Edistribution system,andOnedieselgenerator with:1.Adayfueltankcontaining aminimumof70gallonsoffuel.2.Afuelstoragesystemcontaining aminimumindicated volumeof46,000gallonsoffuel,andAPPLICABILITY:

3.Afueltransferpump.MODES5and6.ACI'ION:WilllessthantheaboveminimumrequiredA.C.electrical powersourcesOPERABLE, suspendalloperations involving COREALTERATIONS orpositivereactivity changes*untiltheminimumrequiredA.C.

electrical powersourcesarerestoredtoOPERABLEstatus.SURVEILLANCE REUIREMENTS 4.8.1.2TheaboverequiredA.C.electrical powersourcesshallbedemonstrated OPERABLEbytheperformance ofeachoftheSurveillance Requirements of4.8.1.1.1 and4.8.1~1.2exceptfor!requirement 4.8.1~1.2.a.5.Forpurposeofthisspecification, additionof'waterfromtheRWSTdoesnotconstitute apositivereactivity additionprovidedtheboronconcentration intheRWSTisgreaterthantheminimumrequiredbySpecification 3.1.2.7.b.2.

COOKNUCLEARPLANT-UNIT 2Page3/48-9AMENDMENT ARAN,444459 3/4.0LIMITINGCONDITION FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.8ELECTRICAL POWERSYSTEMSSURVEILLANCE REUIREMENTS Continued Atleastonceper92daysbyverifying that:Thevoltageofeachconnected cellisgreaterthanorequalto2.13voltsunderfloatcharge.Thespecificgravity,corrected to77'F,andfullelectrolyte level(fluidatthebottomofthemaximumlevelindication mark),ofeachconnected cellisgreaterthanorequalto1.200andhasnotdecreased morethan0.03fromthevalueobservedduringtheprevioustest,andTheelectrolyte levelofeachconnected cellisbetweenthetopoftheminimumlevelindication markandthebottomofthemaximumlevelindication mark.C.Atleastonceper18monthsbyverifying that:1.Thecells,cellplatesandbatteryracksshownovisualindication ofphysicaldamageorabnormaldeterioration, Thecell-to-cell andterminalconnections areclean,tight,freeofcorrosion andcoatedwithantieorrosion

material, 3.Thebatterychargerwillsupplyatleast140amperesatgreaterthanorequalto250voltsforatleast4hours.Atleastonceper18months,performabatteryservicetestduringshutdown(MODES5or6),byverifying thatthebatterycapacityisadequatetosupplyandmaintaininOPERABLEstatustheactualorsimulated emergency loadsforthedesigndutycyclewhichisbasedonthecomposite loadprofile.Thecomposite loadprofileenvelopes boththeLOCA/LOOP andStationBlackoutprofilesandprovidesthebasisforthetimeslistedinTable4.8-2.Thebatterychargerwillbedisconnected throughout thetest.Thebatteryterminalvoltageshallbemaintained greaterthanorequalto210voltsthroughout thistest.e.Atleastonceper60months,conductaperformance testofbatterycapacityduringshutdown(MODES5or6),byverifying thatthebatterycapacityisatleast80%ofthemanufacturer's rating.Whenthistestisperformed inplaceofabatteryservicetest,amodifiedperformance testshallbeconducted.

Annualperformance testsofbatterycapacityshallbegiventoanybatterythatshowssignsofdegradation orhasreached85%oftheservicelifeexpectedfortheapplication.

Degradation isindicated whenthebatterycapacitydropsmorethan10%fromitscapacityonthepreviousperformance test,orisbelow90%ofthemanufacturer's rating.Ifthebatteryhasreached85%ofservicelife,deliversacapacityof100%orgreaterofthemanufacturer's ratedcapacity, andhasshownnosignsofdegradation, performance testingattwoyearintervals isacceptable untilthebatteryshowssignsofdegradation.

COOKNUCLEARPLANT-UNIT 2Page3/48-13AMENDMENT 448,489,466,46 II~~

3/4.0LIMI'rING CONDITION FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.8ELECTRICAL POWERSYSTEMSD.C.DISTRIBUTION

-SHUTDOWNLIMITINGCONDITION FOROPERATION 3.8.2.4Asaminimum,thefollowing D.C.electrical equipment andbusshallbeenergized andOPERABLE:

1-250-voltD.C.bus,and1-250-voltbatterybankandchargerassociated withtheaboveD.C.bus.APPLICABILITY:

MODES5and6.ACTION:Withlessthantheabovecomplement ofD.C.equipment andbusOPERABLE, establish CONTAINMENT INTEGRITY within8hours.SURVEILLANCE REUIREMENTS 4.8.2.4.1 Theaboverequired250-voltD.C.busshallbedetermined OPERABLEandenergized atleastonceper7daysbyverifying correctbreakeralignment andindicated poweravailability.

4.8.2.4.2 Theaboverequired250-voltbatterybankandchargershallbedemonstrated OPERABLEperSurveillance Requirement 4.8.2.3.2.

ICOOKNUCLEARPLANT-UNIT 2Page3/48-15AMENDMENTS, ae,m Iv,~t 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.9REFUELING OPERATIONS STORAGEPOOLVENTILATION SYSTEM"LIMITINGCONDITION FOROPERATION 3.9.12Thespentfuelstoragepoolexhaustventilation systemshallbeOPERABLE.

APPLICABILITY:

Wheneverirradiated fuelisinthestoragepool.ACTION:a.Withnofuelstoragepoolexhaustventilation systemOPERABLE, suspendalloperations involving movementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepool+

untilatleastonespentfuelstoragepoolexhaustventilation systemisrestoredtoOPERABLEstatus'.Theprovisions ofSpeciflcations3.0.3 and3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.9.12Theaboverequiredfuelstoragepoolventilation systemshallbedemonstrated OPERABLE:

a.Atleastonceper31daysbyinitiating flowthroughtheHEPAfilterandcharcoaladsorbertrainandverifying thatthetrainoperatesforatleast15minutes.AtleastonceperISmonthsor(1)afteranystructural maintenance ontheHEPAfilterorcharcoaladsorberhousings, or(2)following

painting, fireorchemicalreleaseinanyventilation zonecommunicating withthesystem,by:1.Deleted.2.Verifying thatthecharcoaladsorbers remove299%ofahalogenated hydrocarbon refrigerant testgaswhentheyaretestedin-placeinaccordance withANSIN510-1980 whileoperating theexhaustventilation systemataflowrateof30,000cfmk10%.'Thecranebayroii-updoorandthesouthdooroftheauxiliary buildingcranebaymaybeopenedunderadministrative controlduringmovementoffuelwithinthestoragepoolorcraneoperation withloadsoverthestoragepool."SharedsystemwithD.C.Cook-Unit1.+Thisdocsnotincludethemainloadblock.Forpurposesofthisspecification, adeenergized mainloadblockneednotbeconsidered aload.COOKNUCLEARPLANT-UNIT 2Page3/49-12AMENDMENT 444 5.0DESIGNFEATURES5.6FUELSTORAGE Continued CRITICALITY-SPENTFUELContinued Theequivalent reactivity criteriaforRegion2andRegion3isdefinedviathefollowing equations:

IForReion2Stora eMinimumAssemblyAverageBurnupinMWD/MTU=-22,670+22,220E-2,2608

+149E3ForReion3StoraeMinimumAssemblyAverageBurnupinMWD/MTU=-26,745+18,746E-1,631E'98.4EiWhereE=InitialPeakEnrichment 5.6.1.2MaximumNominalFuelAssemblyEnrichment Wt.%U-235FuelstoredinthespentfuelstorageracksshaHhaveanominalfuelassemblyenrichment asfollows:Description 1)Westinghouse 2)Exxon/ANF 3)Westinghouse 4)Exxon/ANF15x15STD15x15OFA15x1517x17STD17x17OFA17x17V517x174.954.954.954.95COOKNUCLEARPLANT-UNIT 2Page54AMENDMENT 4k,49k,447,483,498 5.0DESIGNFEATURESFigure5.6-3intentionally deleted.COOKNUCLEARPLANT-UNIT 2Page5-8

~'I~Q~I0IIeaIIlkfiiP'I'I]lal

<Ii6.0ADMINISTRATIVE CONTROLS6.3FACILITYSTAFFUALIFICATIONS 6.3.1Eachmemberofthefacilistaffshtyallmeetorexceedtheminimumqualifications ofANSIN18.1-1971 forcomparable positions, exceptfor(1)thePlantRadiation Protection Manager,whoshallmeetorexceedqualifications ofRegulatory Guide1.8,September 1975,(2)theShiftTechnical Advisor,whoshallhaveabachelor's degreeorequivalent inascientific orengineering discipline withspecifictraininginplantdesign,andresponseandanalysisoftheplantfortransients andaccidents and,(3)theOperations Superintendent, whomustbequalified asspecified inSection6.2.2.g.6.4TRAINING6.4.1Aretraining andreplacement trainingprogramforthefacilitystaffshallbemaintained underthedirection oftheTrainingManagerandshallmeetorexceedtherequirements andrecommendations ofSection5.5ofANSIN18.1-1971 and10CFRPart55.6.5REVIEWANDAUDIT6.5.1PLANTNUCLEARSAFETYREVIEWCOMMITTEE PNSRCFUNCTIONThePNSRCshallfunctiontoadvisetheSiteVicePresident/Plant Manager,ordesignee, onallmattersrelatedtonuclearsafety.COMPOSITION 6.5.1.2ThePNSRCshallbecomposedofAssistant PlantManagers, Department Superintendents, orsupervisory personnel reporting directlytotheSiteVicePresident/Plant Manager,Assistant PlantManagersorDepartment Superintendents.

Themembership shallrepresent thefunctional areasoftheplant,including, butnotlimitedtoOperations, Technical Support,Licensing, Maintenance andRadiation Protection.

ThePNSRCmembership shallconsistofatleastoneindividual fromeachoftheareasdesignated.

Allmembers,including theChairmanandhisalternates, themembersandtheiralternates, shallbedesignated bytheSiteVicePresident/Plant Manager.PNSRCmembersandalternates shallmeetorexcccdtheminimumqualifications ofANSIN18.1-1971Section4.4forcomparable positions.

Thenuclearpowerplantoperations individual shallmeetthequalifications ofSection4.2.2ofANSIN18.1-1971 exceptfortherequirement toholdacurrentSeniorOperatorLicense.Theoperations individual mustholdorhaveheldaSeniorOperatorLicenseorhavebeencertified forequivalent senioroperatorknowledge atCookNuclearPlantorasimilarreactor.Themaintenance individual shallmeetthequalifications ofSection4.2.3ofANSIN18.1-1971.

COOKNUCLEARPLANT-UNIT 2Page6-4AMENDMENT 34,447,438,4',4VS,493 ATTACHMENT 4TOAEP:NRC:0433Q 4EVALUATION OFSIGNIFICANT HAZARDSCONSIDERATION Attachment 4toAEP:NRC:0433Q Page1Evaluation ofSinificantHazardsConsideration TheLicenseehasevaluated thisproposedamendment anddetermined thatitinvolvesnosignificant hazardsconsideration.

According to10CFR50.92(c),

aproposedamendment toanoperating licenseinvolvesnosignificant hazardsconsideration ifoperation ofthefacilityinaccordance withtheproposedamendment wouldnot:1.involveasignificant increaseintheprobability ofoccurrence orconsequences ofanaccidentpreviously evaluated; 2.createthepossibility ofanewordifferent kindofaccidentfromanypreviously analyzed; or3.involveasignificant reduction inamarginofsafety.TheLicenseeproposestomakeadministrative changestoseveraltechnical specifications (T/S)forDonaldC.CookNuclearPlantunit1andunit2.Theproposedchangesinclude:(1)revisingboronsamplingrequirements inmode6;(2)deletingareference toobsoleteequipment inafootnote; (3)deletingaredundant figure;(4)correcting areference toanotherrequirement; (5)deletingobsoletenotes;(6)addingtosurveillance requirements; (7)clarifying instrumentation configuration; and(8)correcting typographical errors.Thesechangesareproposedtoremoveobsoleteinformation, provideconsistency betweenunit1andunit2,provideconsistency withtheStandardTechnical Specifications, provideclarification, andcorrecttypographical errors.Thedetermination thatthecriteriasetforthin10CFR50.92aremetforthisamendment requestisindicated below.1.Doesthechangeinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated?

Theproposedchangeforboronsamplingrequirements inmode6doesnotaffecttheprobability ofafuelhandlingaccident.

Theunlikelyeventofafuelassemblybeingmisloaded isindependent ofthesamplingfrequency forfuelpoolboronconcentration.

Ithasnoimpactontheeventinitiator, whichisahumanerrorwhilepositioning afuelassembly.

Thechangehasnoimpactonthe*assumptions forafuelhandlingaccident.

Theboronconcentration requirement isnotchanged;thereissufficient boroninthefuelstoragepooltomaintaink,qqbelow0.95toprecludeaninadvertent criticality.

Therefore, theconsequences oftheaccidentwillbemitigated aspreviously evaluated.

The72-hourmaximumintervalbetweensamplesismaintained.

Operating experience hasshown72hourstobeadequate.

Removingtheadditional limitation ofsamplingatleastthreetimesperweekwouldallowthesampletobecollected twoorthreetimesperweek,consistent withthemaximum72-hourinterval.

Thisisacceptable becauseboronconcentration changesoccurslowlyduetothelarge 1

Attachment 4toAEP:NRC:0433Q Page2volumeofwaterinthesystemandrelatively smallvolumesofdilutionsources.Theconsequences arenotincreased becausetherearenochangestothespentfuel,shielding (water),orsystemsusedtomitigatetheconsequences ofanaccident.

Additionally, thereisnochangeinthetypesorsignificant increaseintheamountsofanyeffluents releasedoffsite.Deletingtheredundant figureforequivalent reactivity criteriaforregionsinthespentfuelstorageracksdoesnotimpactthestoragerequirements becausetheequations provideequivalent requirements.

Theunlikelyeventofafuelassemblybeingmisloaded isindependent ofthecharacteristics ofthespentfuelinthepool.Ithasnoimpactontheeventinitiator, whichisahumanerrorwhilepositioning afuelassembly.

Thechangehasnoimpacttheassumptions forafuelhandlingaccidentbecausethefuelstoragerequirements arenotchanged.Theconsequences ofanaccidentarenotincreased becausethefuelstoragerequirements arenotchangedandnootherchangesaremadetosystemsthatmitigatetheconsequences ofanaccident.

Theproposedchangestocorrectareference toanotherrequirement, deleteobsoletenotes,revisethenameofdrummingroomroll-updoor,andcorrecttypographical errorsareconsidered administrative.

Thereference leadstoasectionthatnolongerexists;theproposedchangecorrectstheerror.Thenotespermitted exceptions torequirements, andtheyarenolongerrequired.

Thenormalrequirements haveappliedsincetheprovisions expired.Deletingthemeliminates extraneous information.

Thereviseddescription ofthedoorreflectsthecurrentuseoftheinstalled door.Correcting thetypographical errorsimprovesreadability.

Thecorrections arenotintendedtochangethemeaning.Thesechangesdonotaffectaccidents described intheUFSAR.Addingnewsurveillance requirements totesttheunit2pumpperformance pursuanttoT/S4.0.5doesnotaffectaccidentinitiators orprecursors.

ThechangereflectsASMEcoderequirements.

Including therequirements inthecorresponding sectionprovidesassurance thatthepumpswilloperateasassumedintheaccidentanalyses.

Assuch,theprobability and'onsequences ofpreviously evaluated accidents isunchanged.

Theproposedchangetothedescription ofinstrumentation configuration isconsidered administrative becausetheconfiguration hadbeenreviewedandapprovedbytheNRCStaff,asdocumented intheSafetyEvaluation Reportforamendment 39forDPR-58andamendment 22forDPR-74.Therearenochangestotheactualplantconfiguration.

Thechangeisintendedtodescribetheinstalled equipment moreclearly.Thechangedoesnotaffecttheprobability andconsequences ofpreviously evaluated accidents becausetheequipment isinstalled andoperatedasdescribed inthecorrespondence relatedtothepreviousamendments.

Basedonthisreview,itisconcluded thattheproposedchangesdonotinvolveasignificant increaseinthe L.

Attachment 4toAEP:NRC:0433Q Page3probability ofoccurrence orconsequences ofanaccidentpreviously evaluated.

2.Doesthechangecreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated' Theproposedchangesremoveobsoleteinformation, provideconsistency betweenunit1andunit2,provideconsistency withtheStandardTechnical Specifications, provideclarification, andcorrecttypographical errors.Thesechangesareconsidered administrative becausetheydonotaffectthedesignoroperation ofanysystem,structure, orcomponent intheplant~Theaccidentanalysisassumptions andresultsareunchanged.

Nonewfailuresorinteractions havebeencreated.Basedonthisreview,itisconcluded thattheproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated.

3.Doesthechangeinvolveasignificant reduction inamarginofsafety?Theproposedchangesareconsidered administrative innature.TheydonotaffectanysafetylimitsorT/Sparameter limits.Theproposedchangesdonotintroduce newequipment, equipment modifications, ornewordifferent modesofplantoperation.

Thesechangesdonotaffecttheoperational characteristics ofanyequipment orsystems.Basedonthisreview,itisconcluded thatnoreduction inthemarginofsafetywilloccurasaresultofthechanges.'nsummary,basedupontheaboveevaluation, theLicenseehasconcluded thatthesechangesinvolvenosignificant hazards'onsideration.

ATTACHMENT 5TOAEP:NRC:0433Q ENVIRONMENTAL ASSESSMENT

Attachment 5toAEP:NRC:0433Q Page1Environmental Assessment TheLicenseehasevaluated thislicenseamendment requestagainstthecriteriaforidentification oflicensing andregulatory actionsrequiring environmental assessment inaccordance with10CFR51.21.TheLicenseehasdetermined thatthislicenseamendment requestmeetsthecriteriaforacategorical exclusion setforthin10CFR51.22(c)(9)

.Thisdetermination isbasedonthefactthatthischangeisbeingproposedasanamendment toalicenseissuedpursuantto10CFR50thatchangesarequirement withrespecttoinstallation oruseofafacilitycomponent locatedwithintherestricted area,asdefinedin10CFR20,orthatchangesaninspection orasurveillance requirement, andtheamendment meetsthefollowing specificcriteria.

(i)Theamendment involvesnosignificant hazardsconsideration.

Asdemonstrated inattachment 4,thisproposedamendment doesnotinvolveanysignificant hazardsconsideration.

(ii)Thereisnosignificant change.inthetypesorsignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite.Asdocumented inattachment 4,therewillbenochangeinthetypesorsignificant increaseintheamountsofanyeffluents releasedoffsite.(iii)Thereisnosignificant increaseinindividual orcumulative occupational radiation exposure.

Theproposedchangeswillnotresultinchangesintheoperation orconfiguration ofthefacility.

Therewillbenochangeinthelevelofcontrolsormethodology usedforprocessing ofradioactive effluents orhandlingofsolidradioactive waste,norwilltheproposalresultinanychangeinthenormalradiation levelswithintheplant.Therefore,

'herewillbenoincreaseinindividual orcumulative occupational radiation exposureresulting fromthischange.

li*

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