ML17331B073

Proposed Tech Specs,Reflecting Administrative & Editorial Changes

ML17331B073
Person / Time
Site:	Cook
Issue date:	11/15/1993
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
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ML17331B072	List: ML17331B071 ML17331B073
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NUDOCS 9312010010
Download: ML17331B073 (71)

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II1~t~TABLE3.3-1Continued DESIGNATION P-7P-8CONDITION ANDSETPOINTWith2of4PowerRangeNeutronFluxChannelsgreaterthanorequalto11%ofRATEDTHERMALPOWERor1of2TurbineFirstStagePressurechannelsgzeaterthanorequalto37psig.With2of4PowerRangeNeutronFluxchannelsgreatezthanorequalto31%ofRATEDTHERMALFUNCTIONP-7preventsordefeatstheautomatic blockofreactortripon:Lowflowinmorethanoneprimarycoolantloop,reactorcoolantpumpunder-voltage andundez<<frequency, tuzbinetrip,pressurizer lowpressure, andpressur-izerhighlevel~wflowinaparticular loopcanbeevidenced byeitheradetectedlowfloworbytheopeningofthereactozcoolantpumpbreaker.P-8preventsordefeatstheautomatic blockofreactortripcausedbyalo~kSWcoolantflowcondition inasingleloop,~P-10With3of4Powerrangeneutronfluxchannelslessthan9%ofRATEDTHERMALPOWER.P-10preventsordefeatsthemanualblockof:Powerrangelowsetpointreactortrip,Intermediate rangereactortrip,andintermediate rangerodstops'rovides inputtoP-7.COOKNUCLEARPLANT-UNIT13/43-9AMENDMENT NO.SSI12093120i00i0 93iii5PDRADOCK050003i5PPDR

~~71~iyh."k,~ryUl 4~qlI~TABLE3.3<<10(Continued)

UntandCommoeaeetectioSystemsDetectorSstemLocatoTotalNumberoDetectors UlCableTunnelsa)Quad1CableTunnelb)Quad2CableTunnelc)Quad3Nd)Quad3Se)Quad3Mf)Quad4peat(x/y)*~arne(x/y)*0/30/40/30/30/30/5Smoke(x/y)*0/40/70/40/30/40/6a)b)d)e)HV-AES-1-AES-2HV-ACRFHV-CIPXHV-CPRf)12-HV-AFX 1Containment+++~

a)RCP1b)RCP2c)RCP3d)RCP4e)CableTraysUlCharcoalFilterVentilation Units0/1~0/1~0/]4+++&0/1~0/]~0/1~C1/01/01/01/058/p~~C*(x/y)SystemprotectsareacommontobothUnits1and.2xisnumberofFunctionA(earlywarningfiredetection andnotification only)instruments.

yisnumberofFunctionB(actuation offiresuppression systemsandearlywarningandnotificatIon)

Instruments.

Originally installed toautomatically delugecharcoalfilters.However,manualactionsarenovnecessary.

Thefiredetection Instruments locatedwithintheContainment arenotrequiredtobeOPERABLEduringtheperformance ofTypeAContainment LeakageRatetests.Thermistors arelocatedwithinallcabletrayswhichcontaincombustible cables,inbothupperandlovercontainment throughout quadrants 1-4.OOKNUCLEARPLANT-UNIT13/43-53aA?KNDMENT NO.kgb',172 OS-CCE00GSUET0~S~U~EMINIMUM.C)SNNELSKXUUEKl.2.3.4.5.6.7.8.9.10.11.12.13.14.15.16.17.1&,Containment PressureReactorCoolantOutletTemperature-Tsoz(WideRange)ReactorCoolantInletTemperature-Tco~(WideRange)ReactorCoolantPressure-Wide RangePressurizer WaterLevelSteamLinePressureSteamGenerator WaterLovel-NarrowRangeRefueling WaterStorageTankWaterLevelBoricAcidTankSolutionLevelAuxiliary Foedwater FlowRateReactorCoolantSystemSubcooling MarginMonitorPORVPositionIndicator

--LimitSwitches***

PORVBlockValvePositionIndicator

--LimitSwitchesSafetyValvePositionIndicator

--AcousticMonitorIncoroThermocouples (CoreExitThermocouples)

ReactorCoolantInventory TrackingSystem(ReactorVesselLevelIndication)

Containment SumpLevelContainment MaterLevel222222/SteamGenerator 1/SteamGenerator 211/SteamGenerator*

1%*1/Valve1/Valve1/Valve2/CoreQuadrantOneTrain(3Channels/Train)

~lebi4h~i44a2SteamGenerator WaterLevelChannelscanbeusedasasubstitute forthecorresponding auxiliary feedwater flowratechannelinstrument.

PPCsubcooling marginreadoutcanbousedasasubstitute forthesubcooling monitorinstrument.

Acousticmonitoring ofPORVposition(1channelperthreevalves-headereddischarge) canbeusedssasubstitute forthePORVIndicator

-LimitSwitchesinstruments.

r--the=4ev~mns mdi~t~cous R=107WwCOOKNUCLEARPLANT-UNIT13/43-55Amendment No.406,4&t,168 1ssS1'TABLE4.3-7POST<<ACCIDENT MONITORING INSTRUMENTATION SURVEILIANCE REUZK2KNTSINSTRUMENT CHANNELCHANNELCNBCNCALTBBATTON 1.Containment'ressure 2.ReactorCoolantOutletTemperature-HOT(VideRange)3.ReactorCoolantInletTemperature-TCO(WideRange)4.RealcorCoolantPressure-Wide Range.5.Pressurizer WaterLevel6.SteamLinePressure7.SteamGenerator WaterLevel-Narrow Range8.RWSTWaterLevel9.BoricAcidTankSolutionLevel10.Auxiliary Feedwater FlowRate11.Reactor CoolantSystemSubcooling MarginMonitor12.PORVPositionIndicator

-LimitSwitches13.PORVBlockValvePositionIndicator-LimitSwitches14.Safety ValvePositionZndicator-AcousticMonitor15.Incore Thermocouples (CoreExitThermocoup 16.Reactor CoolantInventory TrackingSystem(ReactorVesselLevelTndication) 17.Containment SumpLevel~18.Containment WaterLevelMMMMMMMMM~Mles)MM(2)MMRRRRRRRRRRRR(l)R(3)RR(1)Partialrangechannelcalibration forsensortobeperformed belowP-12inMODE3.(2)WithonetrainofReactorVesselLevelIndication inoperable, Subcooling MarginIndication andCoreExitThermocouples maybeusedtoperformaQGQKELCHECKtoverifytheremaining ReactorVesselIndication trainOPERABLE.

s(3)Coaplerion ofohannelelaibrarion forsensorseobeperforned belowP-13inMODE3.-~heseDmeruments=wk3.-1Mecome=eke COOKNUCLEARPLANT-UNZT13/43-56AMENDMENT NO.$$,144

~xs~WSSC00DC~~ONODDieselGenerator lABRoomDieselGenerator 1CDRoomDieselGenerator FuelOilPumpRoom4KVSwitchgear RoomsControlRodDrive,Transf.Switchgear RoomsEngineered SafetySwitchgear RoomSwitchgear RoomCableVaultCross-zoned HeatCross-zoned HeatHeatManualManualCross-zoned Ionization andInfraredAuxiliary CableVaultControlRoomCableVault(Backup)*

Penetration CableTunnelQuadrant1Penetration CableTunnelQuadrant2Penetration CableTunnelQuadrant3NPenetration CableTunnelQuadrant3MPenetration CableTunnelQuadrant3SPenetration CableTunnelQuadrant4Ionization ManualManualManualManualManualManualManual2*ControlRoomCableVaultCOSystemi'sonlyrequiredtobeoperablewhentheCableVaultHalonSystemis-operable.

COOKNUCLEARPLANT-UNIT13/47-41AMENDMENT NO.173 II~A~.REFUELING OPERATIONS CRANETRAVEL"SPENTFUELSTORAGEPOOLBUILDING*

LIMITINGCONDITION FOROPERATION 3.9.7Loadsinexcessof2,500poundsshallbeprohibited fromtraveloverfuelassemblies inthestoragepool.Loadscarriedoverthespentfuelpoolandtheheightsatwhichtheymaybecarriedoverrackscontaining

.fuelshallbelimitedinsuchawayastoprecludeimpactenergiesover24,240in.-lbs.,

iftheloadsaredroppedfromthecrane.APPLICABILITY:

Withfuelassemblies inthestoragepool.ACTION:Withtherequirements oftheabovespecification notsatisfied, placethecraneloadinasafecondition.

Theprovisions ofSpecification 3.0.3arenotapp'licable.

SURVEILLANCE REUIREMENTS 4.9.7.1Craneinterlocks whichpreventcranetravelwithloadsinexcessof2,500poundsoverfuelassemblies shallbedemonstrated OPERABLEwithin7dayspriortocraneuseandatleastonceper7daysthereafter duringcraneoperation; 4.9.7.2Thepotential impactenergyduetodroppingthecrane'sloadshallbedetermined tobe(24,240in.-lbs.priortomovingeachloadoverrackscontaining fuel.*SharedsystemwithD.C.COOK-UNIT2D.C.-COOK-UNIT13/49-8Amendment No.797,113 RADIOACTIVE EFFLUENTS GASEOUSRADWASTETREATMENT LIMITINGCONDITION FOROPERATION 3.11.2.4Thegaseousradvastetreatment systemandtheventilation exhausttreatment systemshallbeusedtoreducetheradar.oactive materials ingaseousvasteprioxtotheirdischarge vhentheproJected gaseouseffluentaixdosesduetogaseouseffluentreleasestounrestricted ax'eas(SeeFigure5.13)vhenaveragedover31days,vouldexceed0.2mradforgammaradiation and0.4mradforbetaradiation.

Theventilation exhausttreatment systemshallbeusedtoreduceradioactive materials ingaseousvastepriortotheirdischarge vhentheproJected dosesduetogaseouseffluentreleasestounrestricted areas(SeeFigure$.1-3)vhenaveragedover31daysvouldexceed0.3mremtoanyorgan.APPLICABILITY:

Atalltimes.ACTION:a.Vi.thgaseousvastebeingdischarged vithouttreatment andinexcessoftheabovelimits,prepaxeandsubmittotheCommission vithin30days,puxsuanttoSpecification 6.9.2,aSpecialReportwhichincludesthefolloving information:

Identification oftheinoperable equipment orsubsystems andthereasonforinoperability.

2.Action(s) takentorestoxetheinoperable equipment tooperablestatus.b.Theprovisions ofSpecifications 3.0.3and3.0.4arenotapplicable.

SURVEILLANCE REUZREHENTS 4.11.2.4DosesduetogaseousreleasestoUNRESTRICTED AREASshallbeproJected atleastonceper31daysinaccoxdance viththeODCM,wheneverthegaseouswastetreatment systemorventilation exhausttreatment systemisnotoperational.

COOKNUCLEARPLANT-UNIT13/411-12AMENDMENT NO.QA/4 gl~/t~<<'hmeeeI,err

+el~32.l~l.III~e~e)ePf)rue"eLV~if~eanel BeoreI'fe~)be~en;frt Be.unf6..')~~~~~~~~i/~/'r~tl'/.~~~I~t0~=t~'rf~aCrrfn~~~0~~e'eedeef~w~e~~ro~7//~e'e~~1/~~.'//~~~~~f~~pl.iifneiton

'~~~pJC~~~1:~I~..I.r$vleeI)0~e~4+)~~~ee.ee'ee../OONALOC.COOKNUCLEARPLANTEXCLUS10N AREAFlG.5.1-1:-;7;e~ffSe~~y0~

DESIGNFEATURESCAPACITY5.6.4Thefuelstoragepoolisdesignedandshallbemaintained witha!storagecapacitylimitedtonomorethan3613fuelassemblies.

5.7SEISMICCLASSIFICATION 5.7.1Thosestructures, systemsandcomponents identified a'sCategoryIItemsintheFSARshallbedesignedandmaintained totheori.ginal designprovisions contained intheFSARwithallowance fornormaldegradati.on pursuanttotheapplicant Surveillance Requirements.

5.8METEOROLOGICAL TOV7ERLOCATION35.8.1Themeteorological towershallbelocatedasshownonFigure5.1P.5.9COMPONENT CYCLICORTRANSIENT LIMIT5.9.1Thecomponents identified inTable5.9-1aredesignedandshallbemaintained withinthecyclicortransient limitsofTable5.9-1.COOKNUCLEARPLANT-UNIT15-9AMENDMENT No.8,127I169 ADMINISTRATIVE CONTROLS6.1RESPONSIBILITY 6.1.1ThePlantManagershallberesponsible foroverallfacilityoperation andshalldelegateinvritingthesuccession tothisresponsibility duringhisabsence.6.1.2TheShiftSupervisor (orduringhisabsencefromthecontrolzoomcomplex,adesignated individual) shallberesponsible forthecontrolroomcommandfunction.

hmanagement directive tothiseffectsignedbytheVicePresident

-NuclearOperations shallbezeissuedtoallstationpersonnel onanannualbasis.6.2ORGANIZATION ONSZTEhNDOFFSITEORGANIZATIONS 6.2.1Onsiteandoffsiteorganizations shallbeestablished forunitoperation andcozporate management, respectively.

Theonsiteandoffsiteorganizations shallincludethepositions foractivities affecting thesafetyofthenuclearpoverplant.Linesofauthority, zesponsibQiry, andcommunication shallbeestablished anddefinedforthehighestmanagement.

levelsthzoughintermediate levelstoandincluding alloperating organization positions.

Theserelationships shallbedocumented andupdated,asappropriate, intheformoforganizational charts.Theseorganizational chartsvillbedocumented intheandupdatedinaccordance vith10CZR50.71(e).

vP'~4~b.ThePlantManagershallberesponsible foroverallunitsafeoperation and.shallhavecontroloverthoseonsiteactivities necessary forsafeoperation andmaintenance oftheplant..c.TheVicePresident

-NuclearOperations shallhavecorporate responsibi.lity foroverallplantnuclearsafetyandshalltakeanymeasuresneededtoensureacceptable performance ofthestaff~inoperating, maintaining, andproviding technical supporttotheplanttoensuzenuclearsafety.d.Theindividuals vhotraintheoperating staffandthosewhocarryouthealthphysicsandquality.assurance functions mayreporttotheappropriate onsitemanager;hovever,theyshallhavesufficient organizational freedomtoensuretheirindependence fromoperating pressures.

FACILITYSTAFF6.2.2TheFacilityorganization shallbesub]ecttothefollovtng:

a.Each.ondutyshiftshallbecomposedofatleasttheminimumshiftcrewcomposition shovninTable6.2-1.COOKNUCLEARPLANT-UNIT16-1AMENDMENT NO.7',gqr,154 l~acADMINISTRATIVE CONTROLS6.3FACILXTTSTAFFUALIFICATIONS 6.3.LEachmemberofthefacilietionsofAHS971ystaffshallmeetorexceedthaminimumqualificaXN18.11forcomparable positions, exceptfor(1)chePlantRadiation Protection Manager,vhoshallmeetorexceedqualifications ofRegulatory Guide1.8,September 1975,(2)theShiftTechnical Advisor,vhoshallhaveabachelor's degreeozequivalent inascientific orenginaexing discipline viehspecifictzaininginplanedesign,andresponseandanalysisoftheplantfortzansients andaccidents and,(3)theOperations Superintendent, vhomustholdorhaveheldaSeni.orOperatorLicenseasspecifi.ed inSection6.2.2.h.6.4TRAZHING6.4.1Aretraining andreplacement trainingpxogramforehefacilitystaffshallbemaintained underthedirection oftheTrainingManagerandshalLmeetorIexceedtharequirements andrecommendations ofSection5.5ofANSIH18.1-1971 and10CFRPare55.6.5REVIEWAHDAUDIT6.5.1PLANTNUCLEARSAFETYREVIEWCOMMITTEE PHSRCFUNCTION6.5.L.LThePHSRCshalIfunctiontoadvisethePlantManageronallmattersrelatedconucleazsafety.COMPOSITION 6.5.1.2ThePNSRCshallbecomposedofhssistanc PlantManagers,'epartment Superintendents, orsupervisory personnel reporting directlytothePlantManager,Assistant PLantManagersorDepartment Superincandents fromehefunctional areaslistedbelov:Licensing hctivt.ties Safety6Assessmanc Operaeions Technical SupportRadiation Protection Maintenance TheChairman, hisalternate and'othermembersandchairalternates.

ofchePHSRCshallbedesignated bythePlaneManagez.ZnadditiontotheChairman, thePNSRCmembership shallconsistofoneindividual fromeachoftheareasdesignated above.kPNSRCmembersandaltexnaces shallmeetorexceedtheminimumqualificati.ons ofAHSXNL8.1-1971 Section4.4forcompazabla posieions.

Thenuclearpoverplantoperations.

individual shallmeetehequalifications ofSection4.2.2ofAHSLN18.1-1971 excepeforehezequirement toholdacuzzancSeniorOperaeorLicense.Thaoperaeions individuaL museholdorhaveheldaSeniorOperacorLicenseatCookNuclearPlaneor~similarreactor.Themaintenance individual shallmeetthequalifications ofSection4.2.3ofANSXN18.1-1971.

COOKNUCLEARPLANT-UNIT16-4AMENDMEHT NO.P'g,f$>$/7,1U I~~INSTRUYEN TATIONEASES34.3.3.5REMOTE'HUTDOQN INSTRUMENTATION OPERABILITY oftheremoteshutdowninstrumentation ensuresthatsufficient capability isavailable topermitshutdownandmaintenance ofHOTSTANDBYofthefacilityfromlocations outsideofthecontrolroon.Thiscapability isrequiredintheeventcontralroomhabitability islostandi.sconsistent withGeneralDesignCri.teria 19of10CFR50.34.3.3.5.1APPENDIXRREMOTESHUTDOMHINSTRUMENTATION TheOPERABILITY oftheAppendixRremoteshutdowninstrumentation ensuresthatsufficient instrumentation isavailable topermitshutdownofthefacilitytoCOLDSHUTDORfcondi.tions atthelocalshutdownindication (LSI)panel.Intheeventofafire,normalpowertotheLSIpanelsmaybelast.Asaresult,capability torepairtheLSIpanelsframUnit2hasbeenprovided.

Ifthealternate powersupplyisnotavailable, firewatcheswillbeestablished inthosefireareaswherelossafnormalpowertotheLSIpanelscouldoccurintheeventoffire.Thiswillconsistofeitherestablishing continuous firewatchesorverifying, OPERABILITY offiredetectors perSpecification 4.3.3.7andestablishing hourlyfirewatches.Thedetailsofhowthesefirewatchesaretobeimplemented areincludedin,aplantprocedure.

34.3.3.7FIREDETECTION INSTRUMENTATION SYSTEMSDETECTORS OPERABILITY ofthefiredetcctian systcms/detectors ensuresthatadequatedetection capability i.savailable forthepromptdetection offires.Thiscapability isrequiredinordertodetectandlocatefiresintheircarlystages.Promptdetection ofthefires.willreducethepotential fordamagetosafetyrelatedsystemsorcomponents intheareasofthespecified systemsandisanintegralelementintheoverallfacilityfireprotection program.Intheeventthataportionofthefiredetection systemsi.sinoperable, theACTIONstatements providedmaintainthefacility's fireprotection programandallowsfarcontinued operation ofthefacili.ty untiltheinoperable system(s)/detectar(s) arerestoredtoOPERABILITY.

However,i.tisnotourintenttorelyuponthecompensatory actionforanextendedperiodoftimeandactionwillbetakentorestoretheminimumnumberofdetectors toOPERABLEstatus~ithinareasonable period.34.3.3.8POST-ACCIDENT INSTRUMENTATION TheOPERABILITY ofthepost-accident instrumentati.on ensuresthatsufficient information isavailable onselectedplantparameters tomonitorandassessthesevariables duri.ngandfollowing anaccident.

4C4&%44~ch edl13rO~COOKNUCLEARPLANT-UNIT1.B3/43-6AMENDMENT NO.7p es~~~lEFUELINCOPERATIONS BASES34.9.10AND34.9.11VATERLEVEL-REACTORVESSELANDSTORAGEPOOLTherestrictions onminimumwaterlevelensurethatsufficient waterdepthisavailable tozemove99ioftheassumed10%iodinegapactivityreleasedfromtheruptureofanirzadiated fuelassembly.

Theminimumvacezdepthisconsistent withtheassumptions ofcheaccidentanalysis.

MaterlevelabovethevesselflangeinMODE6villvaryasthezeaccorvesselheadandthesysteminternals areremoved.The23feetofvaterarerequiredbeforeany'ubsequent movementoffuelassemblies oz'ontrol rods."34.9.12STORAGEPOOLVENTILATION SYSTEMThelimitations onthestoragepoolventilation systemensurechatallzadioaccive materialreleasedfromanirradiated fuelassemblywillbefilteredthroughtheHEPAfiltersandcharcoaladsorberpriortodischarge totheatmosphere.

TheOPERABILITY ofthissystemandtheresulting iodinezemovalcapacityareconsistent withtheassumptions oftheaccidentanalyses.

The1980versionofANSIN510isusedasatastingguide.Thisstandard, however,isintendedtoberigorously appliedonlytosyscemswhich,unlikethestoragepoolventilacion system,aredesignedtoANSIN509standards.

Forthespecificcaseoftheaireaerosol mixinguniformity testrequiz'ed byANSIN510asaprerequisite toin-placeleaktestingofcharcoalandHEPAfilters,theair-aerosol uniformmixingcastacceptance cr'ariawerenocrigozously met.Forthisreason,astatistical correction factorvillbeappliedtoapplicable surveillance caseresultsvharerequired.

InordercomaintaintheminimumnegativepressurerequiredbyTechnical Specifications (1/8inchM.G.)duringmovemencoffuelvichinthestoragepoo'1orduringcraneopezacion vithloadsoverthepool,thecz'anebayroll-updoorandthedrummingroomroll-updoor,locatedonthe609-footelevation oftheauxiliary'uilding, mustbeclosed.Hovever,theymaybeopenedduringtheseoperations underadministrative control.Ifchacranebaydoorneedstobeopenedduringfuelmovement, anexampleofanadministzative controlmightbetostationanindividual atthedoorwhowouldbeincosssunioation withpersonnel in'hespentfuelpoolareaandoouldthedoorwhenpassagewasoscompleted orintheeventofanemergency, Forthedrummingroomdoor,anexampleofanadministrative concz'olmightbetorequirethadoorcobez'eclosed afternormalingressandegressofpersonnel ormaterial, ortostationanindividual atthedoorifthedoorneedscoremainopenforanextendedperiodoftime.Shouldthedoorsbecomeblockedorstuckopenvhileunderadministzative contzol,Technical Specification requirements villnocbeconsidered tobeviolatedprovidedtheActionStatement requirements ofSpecification 3.9.12.az'aexpeditiously

followed, i.e.,movement.

offuelwithinthestoragepool.orcraneoperation vithloadsoverchapoolisexpeditiously suspended.

D.C.COOK-UNIT1B3/49-3Amendment No.7gp124 OTABLE3.3-1Continued REACTORTRIPSYSTEMINSTRUMENTATION IFUNCTIONAL UNITH16..Undervoltage-Reactor CoolantPumpsTOTALNO.OFCHANNELS4-1/busCHANNELSTOTRIPMINIMUMCiiANNELSOPERABLEAPPLICABLE MODESACTION17.Underfrequency-Reactor CoolantPumps4-I/bus31iti.Turbin<<Trip A.LowFluidOilPressureB.TurbineStopValveClosure19.SafetyInjection InputfromESF),220.ReactorCoolantPumpBreakerPositionTripAboveP-721.ReactorTripBreakers1/brcaker1/breaker peroperat-ingloop1,2,3*,4*,5*1,13,1422.Automatic TripLogic2i+'K0 II\'1~~I ouedWith2of4PowerRangeNeutronFluxChannels>11$ofRATEDTHERMALPOWERor1of2PressureBeforetheFirstStagechannels>51psig.P-7preventsordefeatstheautomatic blockofreactortripon:Lowflowinmorethanoneprimarycoolantloop,~reactorcoolantpumpunder-voltage andunder-frequency, turbinetrip,pressurizer lowpressure, andpressurizer highlevel.Lowflowinaparticular loopcanbeevidenced byeitheradetectedlowfloworbytheopeningofthereactorcoolantpumpbreaker.P-8With2of4PowerRangeNeutronFluxchannels>31%ofRATEDTHERMAL.POWER.P-8preventsordefeatstheautomatic blockofreactortripcausedbybar-alowcoolantflowcondition inasingleloop,P-10'Pith3of4PowerRangeNeutron.Fluxchannels<9SofRATEDTHER.fALPOWER.?-10preventsordefeatsthemanualblockof:Powerrangelowsetpointreactortrip,Intermediate rangereactortrip,andintermediate rangerodstops~ProvidesinputtoP-7.D.C.COOK-UNIT2~~~~3/43-8.AMENDMENT NO.Ns107 I~~I~~

0-CC00GSUE0~lSTUHEHICIAIS081.2.3.4.5.6.7.8.9.10.11.12.13.14.15.16.17.1S.Containment PressureReactorCoolantOutletTemperature

-Tso<(MideRange)ReactorCoolantInletTemperature

-Tco~(WideRange)ReactorCoolantPressure-WideRangePressurizer WaterLevelSteamLinePressureSteamGenerator MaterLevel-NarrowRangeRefueling WaterStorageTankMaterLevelBoricAcidTankSolutionLevelAuxiliary Feedwater FlowRateReactorCoolantSystemSubcooling MarginMoni.torPORVPositionIndicator

-LimitSwitches~*

PORVBlockValvePositionIndicator

-LimitSwitchesSafetyValvePositionIndicator

-AcousticMonito&~+-

IncoreThermocouples (CoreExitThermocouples)

ReactorCoolantInventory TrackingSystem(ReactorVesselLevelIndication)

Containment SumpLevelContainment WaterLevel2'2222/Stea'mGenerator 1/SteamGenerator 211/SteamGenerator*

1**1/Valve1/Valve1/Valve2/CoreQuadrantOneTrain(3channels/Train)

SteamGenerator MaterLevelChannelscan:.beusedasasubstitute forthecorresponding auxiliary feedwater flowratechannelinstrument; PPCsubcooling marginreadoutcanbeusedasasubsti.tute forthesubcooling monitorinstrument.

Acousticmonitoring ofPORVposition(1channelperthreevalves-headereddischarge) canbeusedasasubstitute forthePORVIndicator

-LimitSwitchesinstruments.

d-~rn:eplnce&an&becon~perenional.

Thmchednle-for nodt4lcaeion orre-pla-accent fothet-ra-netnlrceaCOOKNUCLEARPLANT-UNIT23/43-46Amendment No,QR,0$,7gg,151 INSTRUMENT CHANNELCHANNELCHECKCAI.lBRATIOH 1.Containment Pressure2.ReactorCoolantOutletTemperature

-T(WideRange)3.ReactorCoolantInletTemperature

-TLD(WideRange)HOT4.ReactorCoolantPressure-WideRangeCOLD5.Pressurizer WaterLevel6.SteamLinePressure'j.SteamGenerator WaterLevel-NarrowRange8.RWSTWaterLevel9.IctericAcidTankSolutionLevel10.Auxiliary Feedwater FlowRatell.ReactorCoolantSystemSubcooling MarginMonitor12.PORVPositionIndicator

-LimitSwitches13.PORVBlockValvePositionIndicator

-LimitSwitches14.Saf'etyValvePositionIndicator

-AcousticMonitor15.IncoreThermocouples (CoreExitThermocouples)~

16.ReactorCoolantInventory TrackingSystem(ReactorVesselLevelIndication) 17.Containment SumpLevel~18.Containment WaterLevel~MMMMMMMMMMMM(2)RRRRRRRRRRRRR(1)R(3)RRPartialrangechannelcalibration forsensortobeperformed belowP-12inMODE3.WithonetrainofReactorVesselLevelIndication inoperable, Subcooling MarginIndication andCoreExitThermocouples maybeusedtoperformaCHANNELCHECKtoverifytheremainI.pg ReactorVesselIndi.cationtrainOPERABLE.

Completion ofchannelcalibration forsensorstobeperformed belowP-12inMODE3.inst~men~+1+-

~fter-t~ve.

pieced-and-become-oIH.

r~nat-.-'She-schedu1a

-for-modi.-fisatian-or-~q+neement-~~

rans~~s~M~bedMn-the-Bases

-.COOKNUCLEARPLANT-UHIT23/43.-47AMENDMENT NO.9g,gg,f3)

E'4~~)

TABLE3.3-,11Unit2andCommonAreaPireDetection SystemsDetec'tion SstemLocationTotalNumberofDetectors Auxiliary Buildinga)Elevation 573b)Elevation 587c)Elevation 609d)Elevation 633e)Elevation 650f)NevFuelSTGEAreaHeat(x/y)+Elame'(x/7)+Smoke(x/y)*-23/OC55/OC41/OC41/OC34/OC4/OCU2East,MainSteamValveEnclosure U2HainSteamLineAreaEl.612(AroundContainment)

U2NESTSValveAreaEl.61228/0+a13/P~2/0U24KVSvitchgeax (AB)U24KFSvitchgear (CD)U2Engr.SafetySystemSvitchgear

&XFMR.Rm.U2CRD,XFHR&Svitchgear Rm.Invertex6ABBttxy.Rms.pQ4e~gQvU2Pressurizer Heater.Rm.U2Di.eselFuelOil.Rm.U2DieselGenerator Rm.2ABU2DieselGenerator Rm.2CDU2DieselGenerator RampCorr.U162AFVPVestibule 0/10/20/20/30/30/20/212/04/02/OC0/50/140/50/17U2ControlRoomU2Svitchgeax CableVaultU2ContxolRm.CableVaultU2Aux.CableVault42/00/10%%+0/130/76~0/6Ul&2ESVBasementAreaU2ESVPump&HCCRms.4/OC9/0CSystemprotectsareacommontobothUnits1and2*(x/y)xisnumberofFunctionA(earlyvaxningfixedetection andnotification only)instruments.

yisnumberofFunctionB(actuati.on offixesuppression systemsandearlyvarningandnotification) instruments.

circuitcontainsbothsmokeand.flame detectors tvocircuitsoffivedetectors each.tvocircui.ts of38detectors each.COOKNUCLEARPLANT-UNIT23/43-52AHNDHENTNn.$X.ZZ$151 III'i N1pREFUELING OPERATIONS CRANETRAVEL-SPENTFUELSTORAGEPOOLBUILDING*

LIMITINGCONDITION FOROPERATION 3.9,7Loadsinexcessof2,500poundsshallbeprohibited fromtravel.overfuelassemblies inthestoragepool.Loadscarriedoverthespentfuelpoolandtheheightsatwhichtheymaybecarriedoverrackscontainina fuelshallbelimited.insuchawayastoprecl'ude impactenergiesover24,240in.-lbs.,

iftheloadsaredroppedfromthecrane.APPLICABILITY:

Withfuelassemblies inthestoragepool.ACTION:Withtherequirementsoftheabo~pecification notsatisfied,.

placethecraneloadinasafecondition.

Theprovisions ofSpecification 3.0.3arenotapplicable.

SURVEILLANCE REUIREMENTS 4.9.7.1.Craneinterlocks

'hichpreventcranetravelwith'oadsinexcessof2,500poundsoverfuelassemblies shallbedemonstrated OPERABLEwithin7dayspriortocraneuseandatleastonceper7daysthereafter duringcraneoperation.

4.9.7.2Thepotential impactenergyduetodroppingthecrane'sloadshallbedetermined tobec24,240in.-lbs.priortomovingeachloadoverrackscontaining fuel.*SharedsystemwithD.C.COOK-UNITD.C.COOK-UNIT2~~j3/49-7Amendment'o.

5?86

~I~REHJELING OPERATIONS SURVEILLANCE REUIREHENTS Continued

~3.Verifying thactheHEPAfilterbanksremovegreaterthanorequalto99'ftheDOPwhentheyaz'etestedin-placeinaccordance withANSIN510-1980 whileoperating theexhaustventilation syscemacaflowz'ateof30,000cfmplusorminus10%.4.Verifying within31daysafterremovalchatalaboratory analysisofacarbonsamplefromeitheracleaseonetestcanisteroracleasecwocarbonsamplesremovedfromoneozthecharcoaladsorbers demonscraces aremovalefficiency ofgreacerchanorequalto90%forradioactive methyliodidewhenthesampleistestedinaccordance withANSIN510-1980 (AS'QID3803-1979, 30C95%R.H.).Thecarbonsamplesnocobcainedfromtesccanisters shallbepreparedbyeither:(a)Emptyingoneentirebedfromaremovedadsorbextray,mixingtheadsorbent thoroughly, andobcaining samplesaclease,cwoinchesincLiamecer andwithalengthequalcothethickness ofchebed,or.(b)Emptyingalongitudinal samplefromaadsorbertray,mixingtheadsorbent thoroughly, andobtaining samplesacleasttwoinchesindiamecerandwichalengchequaltochethickness ofchebed.fSubsequent toreinsailingtheadsorber=ayusedforobtaining thecarbonsample,thesystemshallbedemonscrated OPERA8LEbyalsoverifying thac"hecharcoaladsorbers removegreacerthanorequalto99%ofahalogenaced hydrocarbon xef-igerant testgaswhentheyaretestedin-placeinaccordance withANSIH510-1980 whileoperacing cheventilation systemacaflowraceof~086cfmplusorminus10%.39~Goo5.Verifying asystemflowraceof30,000cfmplusorminus10%duringsystemoperation whentestedinaccordance withANSIH510-1980.

o.Afcez'vexy 720hoursofcharcoal, adsorberoperation byeither:l.Verifying within31daysafterremovalthatalaboracozy analysisozacarbonsampleobtainedfromatestcanisterdemonscraces aremovalefficiency ofgreaterchanorequalto90%forxadioact:ive mechyliodidewhenthesampleistestedinaccordance withANSIH510-1980 (ASTHD3803-1979, 30C,95%R.H.)COOKHUCLF~PLANT-UNIT23/49-13Amendmenc Ho.QE,140

\~IRADIOACTIVE EFFLUENTS GASEOUSRADVASTETREATKENT LYINGCONDITION FOROPERATION 3.11.2.4Thegaseousradvastetreatment systemandtheventilation exhausttreatment systemshallbeusedtoreducetheradioactive materials ingaseousvastepriortotheirdischarge vhentheprojected gaseouseffluentairdosesduetogaseouseffluentreleasestounrestricted azeas(SeeFigure5.1g3)vhenaveragedover31days,vouldexceed0.2mradforgammaradiation and0.4mradfozbetaradiation.

Theventilation exhausttreatment systemshallbeusedtozeduceradioactive materials ingaseousvastepriortotheirdischarge vhentheprojected dosesduetogaseouseffluentreleasestounrestricted areas(SeeFigure5.1-3)vhenaveragedover31daysvouldexceed0.3mremtoanyorgan.APPLICABILITY:

Atalltimes.ACTXON:a~Pithgaseouswastebeingdischazged vithouttreatment andinexcessoftheabovelimits,prepareandsubmittotheCommission within30days,pursuanttoSpecification 6.9.2,aSpecialRepoztvhichincludesthefolloving information:

1.Identification oftheinoperable equipment orsubsystems andthereasonforinoperabi.lizy.

2.Action(s) takentorestoretheinoperable equipment tooperablestatus.b.Theprovisions ofSpecifications 3.0.3and3.0.4arenotapplicable.

SURVEILLANCE REUZRE.'KITS 4.11.2.4DosesduetogaseousreleasestoUNRESTRICTED AREASshallbeprojected atleastonceper31daysinaccordance viththeODQf,wheneverthegaseousvastetreatment systemorventilation exhausttreatment systemisnotoperational.

COORNUCLEARPLANT-UNIT23/411-12 II11~f,I

~'t'~~tt~rIimvA.Vrrr

~Err//e//~o:./rt.//r//~ooe7~~/5'Vsirfiaiitl Baachfir]~~-!.'II@totm:Ia8.Ino~-'>ti6.Ci.~~}o$~v~I".-~='2~~~~~~~~/o'/.'.,:/../t/ov/p/'o~~~I~I'.iiinff ofan~I~~~o~~root~tlf~~tf'II:IfioIf~I~I"rfgtotlotjr~~o~~,IohiooVooI,/ft~~~t/~(Voo~ooy~../OONALOC.COOKNUCLEARPLANTEXCLUSION AREAIIG.5.I-I3;~I'.'i.~~~~of3:.;7raI~

VOLUME5.4.2Thetotalwaterandsteamvolumeofthereactorcoolantsystemis12,612plusorminus100cubicfeetatanominalTavgof70F.05.5METEOROLOGICAL TOWERLOCATION5.5.1Themeteorological towershallbelocatedasshownonFigure5.1-X.5.6FUELSTORAGECRITICALITY

-SPENTFUEL5.6.1.1Thespentfuelstorageracksaredesignedandshallbemaintained with:AKffequivalent tolessthan0.95whenfloodedwitheffunborated water,b.Anominal8.97-inch center-to-center distancebetweenfuelassemblies, placedinthestorageracks.C.Thefuelassemblies willbeclassified asacceptable forRegion1,Region2,orRegion3storagebasedupontheirassemblyaverageburnupversusinitialnominal'nrichment.

Cellsacceptable forRegion1,Region2,andRegion3assemblystorageareindicated inFigures5.6-1and5.6-2.Assemblies thatareacceptable forstorageinRegion1,Region2,andRegion3mustmeetthedesigncriteriathatdefinetheregionsasfollows:1.Region1isdesignedtoaccommodate newfuelwithamaximumnominalenrichment of4.95wt%U-235,orspentfuelregardless ofthedischarge fuelburnup.2.Region2isdesignedtoaccommodate fuelof4.95%initi,alnominalenrichment burnedtoatleast50,000MWD/MTU,orfuelofotherenrichments withequivalent reactivity.

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

COOKNUCLEARPLANT-UNIT2/5-5AMENDMENT NO.SS,ZW,Z2ZZR7,152 II~\4~~

ADMINISTRATIVE CONTROLS6.1RESPONSIBILITY 6.1.1ThePlantManagershallberesponsible foxoverallfacilityoperation andshalldelegateinvzitingthesuccession tothisresponsIbIlity duringhisabsence.6.1.2TheShiftSupexvisor (orduringhisabsencefx'omthecontrolroomcomplex,adesignated indivt.dual) shallberesponsible forthecontrolzoomcommandfunction.

'management directive tothiseffectsignedbytheVicePresident

-NuclearOperations shallbereissuedtoallstationpezsannel onanannualbasis.6.2ORGANIZATION ONSZTEANDOFFSITEORGANIZATIONS 6.2.1.Onsiteandoffsiteorganizations shallbeestablished fox'nitoperatIon andcorporate management, respectively.

TheonsIteand,offsiteorganizatI.ons shallincludetheposI.tions foractivities affecting thesafetyofthenuclearpaverplant.a.Linesofauthority, responsibility, andcommunication shallbeestablished anddefinedfozthehighestmanagement levelsthroughintermediate levelstoandincluding alloperating organization positions.

Theserelationships shallbedocumented andupdated,asappzopriate, intheformoforganizational charts.Theseorganizational chartsvillbedocumented inthe%8gnupdatedinaccordance vith10CFR50.71(e).

tJFiPt-b.ThePlantManagershallberesponsible foroverallunI,tsafeoperation andshallhavecontrolovexthoseonsiteactIvities necessary'or safeoperation andmaintenance oftheplant.C~TheVicePresI.dent

-NuclearOperatIons shallhavecorporate responsibility foroverallplane,nuclearsafetyandshalltakeanymeasuresneededtoensureacceptable performance ofthestaffinopexating, maintaining, andprovidIng technical supporttotheplanttoensuxenuclearsafety.d.Theindividuals vhotraintheoperating staffandthosevhocarryouthealthphysicsandqualityassurance functions mayreporttotheappropriate onsitemanager;hovevex,theyshallhavesuffIcient organizatIonal fxeedomtoensuzetheirindependence fromoperating pressures.

FACILITYSTAFF6.2.2TheFacI.lity organization shallbesub]ecttothefollovtng:

a.Eachondutyshiftshallbecomposedofatleasttheminimumshiftcrevcomposition shovninTable6.2-.1.COOKNUCLEARPLANT-UNIT26-1AMENDMENT NO.Pjt,gl7s138 I1s>~~

I(a~Wg~ADMINISTRATIVE CONTROLS6.3FACILITYSTAFFUALIFICATIONS 6.3,1Eachmemberofthefacilitystaffshallmeetorexceedtheminimumqualifications ofANSIN18.}.-1971 forcomparable positions, exceptfor(1)thePlantRadiation Protection Manager,vhoshallmeetorexceedqualifications ofRegulatory Guide1.8,September 1975,(2)theShiftTechnical Advisor,vho.shallhaveabachelor's degreeorequivalent inascientific ozengineering discipline vithspecifictraininginplantdesign,andresponseandanalysisoftheplantfortransients andaccidents and,(3)theOperations Superintendent, vhomustholdorhaveheldaSeniorOperatorLicenseasspecified inSection6.2.2.h.6.4TRAXNZNG6.4.1Aretraining andreplacement trainingprogramforthefacilitystaffshallbemaintained underthadirection oftheTrainingManagezandshallmeetozlexceedtherequirements andrecommendations ofSection5.5ofANSIN18.1.-1971 and6.5REVIEWANDAUDIT6.5.1PLANTNUCLEARSAFETYREVIEWCOMMITTEE PNSRCFUNCTION6.5,1.1ThaPNSRCshallfunctiontoadvisethePlantManageronallmatters~~~relatedtonuclear'afety.

COMPOSITION 6.5.1.2ThePNSRCshallbecomposedofAssistant PlantManagers, Depaztment Superintendents, orsupervisory personnel reporting directlytothePlantManager,Assistant PlantManagersorDepartment Superintendents fromthefunctional areaslistedbelov:Licensing Activities Safety6Assessment Operations Technical'uppozt Radiation Protection Maintenance TheChairman, hisalternate andothermembersandtheiralternates ofthePNSRCshallbadesignated bythePlantManager.InadditiontotheChairman; thePNSRCmembership shallconsistofoneindividual fromeachofthaareasdesignated above.PNSRCmembersandalternates shallmeetorexceedtheminimumqualifications ofANSXN18.1-1971 Section4.4forcomparable positions.

Thenuclearpoverplantoperations individual shallmeetthequalificationsofSection4.2.2ofANSIN18.1-1971 exceptfor.therequirement toholdacurrentSeniorOperatorLicense.Thaoperations individual mustholdorhaveheldaSeniorOperatorLicenseatCookNuclearPlantorasimilarreactor.Themaintenance individual shallmeetthequalif'cations ofSection4.2.3ofANSIN18.1-1971.

COOKNUCLEARPLANT-UNIT26-4AMENDMENT NO.)P,f77,138 INSTRUMEHTAT IONBASES34.3.3.6POSTACCIDEiTINSTRUMENTATION~

TheOPKQILITY ofthepost-accident instrumentation ensuresthatsufficient information isavailable onselectedplantparameters tomonitorandassessthesevariables duringandfollowing anaccident.

34.3.3.7available orementoftheneutronfluxspatialdi'4onwithinthereactorcore.bilityisreqlxizo1)monitorthecorefluxpatternsthatarerepresehepeakcorepowerdensityand2)limitthecoreraxialpowerprofilesuthetotalpowerpeakin".ismaintained withinacceptable

m'ts.34.3.3.8FIREDETECTION INSTRUMENTATION OPERABILITY ofthefiredetection instrumentation ensuresthat'dequate warningcapability isavailable forthepromptdetection offires.Thiscapability isrequiredinordertodetectandlocatefiresintheirearlystages.Promptde'tection offireswillz'educethepotential fordamagetosafety-related equipment andisanintegralelementintheovez'allfacilityfireprotection program.Intheeventthataportionofthef'edetection instrumentation isinoperable

~theestablishment offrequentfirepatrolsintheaffectedareasisrequiredtoprovidedetection capability untiltheinoperable instrumentation iszesroredtoOPERABILITY.

Useofcontainment temperature monitoring isallowedonceperhourifcontainment fizedetecrion isinoperable.

34.3.3.9RADIOACTIVE L'IUIDEFFLUENTINSTRUMENTATION Theradioactive liquideffluentinstrumentation isprovidetomonitorandcontrol,asapplicable, thereleaseofradioactive materialinliquideffluents duringactualorpotential releases.

Thealarm/trip setpoints fortheseinstruments shallbecalculated inaccordance withNRCapprovalmethodsinthe'ODCMtoensurethatthealarm/trip willoccurprioz'oexceeding thelimitsof10CFRPart20.TheOPER.-'VILITY anduseofth'sinstrumentation

'isconsistent withthez'equiremen"s ofGeneralDesignCriteriaspecified inSection11.3oftheFinalSafetyAnalysisReportfortheDonaldC.CookNuclearPlant.D.C.COOK-UNIT283/43-3Anendment No.61,115,119 Ig~~I

<)~~)~7~IEFUELING'OPERATIONS BASES34.9.9CONTAINMENT PURGEANDEXHAUSTISOLATION SYSTEMTheOPERABILITY ofthissystemensuresthatthecontainment ventandpurgepenetrations willbeautomatically isolatedupondetection ofhighradiation levelswithinthecontainment.

TheOPERABILITY ofthissystemisrequiredtorestrictthereleaseofradioactive materialfromthecontainment atmosphere totheenvironment.

34.9.10AND34.9.11WATERLEVEL-REACTORVESSELANDSTORAGEPOOLTherestrictions onminimumwaterlevelensurethatsufficient waterdepthisavailable toremove99&oftheassumed10%iodinegapactivityreleasedfromtheruptureofanirradiated fuelassembly.

Theminimumwaterdepthisconsistent withtheassumptions oftheaccidentanalysis.'ater levelabovethevesselflangeinMODE6willvaryasthereactorvesselheadandthesysteminternals areremoved.The23feetofwaterarerequiredbeforeanysubsequent movementoffuelassemblies orcontrolrods.34.9.12STORAGEPOOLVENTILATION SYSTEMThelimitations radioactive materialfilteredthroughthetheatmosphere.

Theremovalcapacityareo'nthestoragepoolventilation systemensurethat'llreleasedfromanirradiated

=elassemblywillbeHEPAfiltersandcharcoaladsorberpriortodischarge toOPERABILITY ofthissystemandtheresulting iodineconsistent withtheassumptio..s oftheaccidentanalyses.

The1980versionofANSIN510isusedasatestingguide.Thisstandard, however,isintendedtoberigorously appliedonlytosystemswhich,unlikethestoragepoolventilation system,aredesignedtoANSIN509standards.

Forthespecificcaseoftheair-aerosol mixinguniformity testrequiredbyANSIN510asaprerequisite toin-placeleaktestingofcharcoalandHEPAfilters,theair-aerosol uniform.mixingtestacceptance criteriawerenotrigorously met.Forthisreason,astatistical correction factorwillbeappliedtoapplicable surveillance testresultswhererequired.

InordertomaintaintheminimumnegativepressurerequiredbyTechnical Specifications (1/8inchW.G.)duringmovementoffuelwithinthestoragepoolorduringcraneoperation withloadsoverthepool,thecranebayroll-updoorandthedrummingroomroll-updoor,locatedonthe609-footelevation oftheauxiliary

building, mustbeclosed.However,theymaybeopenedduringtheseoperations underadministrative control.ifth'ecranebaydoorneedstobeopenedduringfuelmovement, anexampleofanadministrative controlmightbetostationanindividual atthedoorwhowould)ej.ncommunication withpersonnel inthespentfuelpoolareaandcould~ma-thedoorwhenpassage,wasC.a)Scomple'ted orintheeventofanemergency.

Forthedrummingroomdoor,anexampleofanadministrative controlmightbetorequirethedoortobereclosedafternormalingressandegressofpersonnel ormateri.aJ,.

ortostationanindividual atthedoorifthedoorneedstoremainopenforanextendedperiodoftime.D.C.COOK-UNIT2B3/49-3Amendment No.$g,111

\It0>~1 ATTACHMENT 3TOAEP:NRC:1137B PROPOSEDREVISEDTECHNICAL SPECIFICATION PAGES l.\~1 TABLE33-1Continued DESIGNATION CONDITION ANDSETPOINTFUNCTIONP-7With2of4PowerRangeNeutronFluxChannelsgreaterthanorequalto11%ofRATEDTHERMAL'OWER or1of2TurbineFirstStagePressurechannelsgreaterthanorequalto37psig.P-7preventsordefeatstheautomatic blockofreactortripon:Lowflowinmorethanoneprimarycoolantloop,reactorcoolantpumpunder-voltage andunder-frequency, turbinetrip,pressurizer lowpressure, andpressur-izerhighlevel.Lowflowinapar'ticular loopcanbeevidenced byeitheradetectedlowfloworbytheopeningofthereactorcoolantpumpbreaker.P-8With2of4PowerRangeNeutronFluxchannelsgreaterthanorequalto31%ofRATEDTHERMALPOWERP-8preventsordefeatstheautomatic blockofreactortripcausedbyalowcoolantflowcondition inasingleloop.With3of4Powerrangeneutronfluxchannelslessthan9%ofRATEDTHERMALPOWER.P-10preventsordefeatsthemanualblockof:Powerrangelowsetpointreactortrip,Intermediate rangereactortrip,andintermediate rangerodstops.ProvidesinputtoP-7.COOKNUCLEARPLANT-UNIT13/43-9AMENDMENT NO.85,4QO a~TABLE33-10(Continued)

Unit1andCommonAreaFireDetection SstemsDetectorSstemLocationTotalNumberofDetectors UlCableTunnelsa)Quad1CableTunnelb)Quad2CableTunnelc)Quad3Nd)Quad3Se)Quad3Mf)Quad4Heat(x/y)*~lame(x/y)*0/30/40/30/30/30/5Smoke(~)*0/40/70/40/30/40/6UlCharcoalFilterVentilation Unitsa)1-HV-AES-1 b)1-HV-AES-2 c)1-HV-ACRF d)1-HV-CIPX e)1-HV-CPRf)12-HV-AFX 0/]*****P/1*****P/1*****0/].**4k%

0/1**+4*0/]**~CUlContainment******

a)RCP1b)RCP2c)RCP3d)RCP4e)CableTrays1/01/01/01/01/0SystemprotectsareacommontobothUnits1and2*(x/y)xisnumberofFunctionA(earlywarningfiredetection andnotification only)instruments.

yisnumberofFunctionB(actuation offiresuppression systemsandearlywarningandnotificati'on) instruments.

Originally installed toautomatically delugecharcoalfilters.However,manualactionsarenownecessary.

Thefiredetection instruments locatedwithintheContainment arenotrequiredtobeOPERABLEduringtheperformance ofTypeAContainment LeakageRatetests,'IThermistors locatedwithincabletrayswhich'ontain combustible cables,inbothupperandlowercontainment throughout quadrants 1-4.COOKNUCLEARPLANT-UNIT13/43-53aAMENDMENT NO.430, TABLE3.3-11POST-ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUMCHANNELSOPERABLE1~2~3~4~5.6.7~8.9.10.11.12.13'4.15.16.17'8.Containment PressureReactorCoolantOutletTemperature-TDT(WideRange)ReactorCoolantInletTemperature-T~i~(WideRange)ReactorCoolantPressure-Wide RangePressurizer WaterLevelSteamLinePressureSteam.Generator WaterLevel-Narrow RangeRefueling WaterStorageTankWaterLevelBoricAcidTankSolutionLevelAuxiliary Feedwater FlowRateReactorCoolantSystemSubcooling MarginMonitorPORVPositionIndicator

-LimitSwitches***

PORVBlockValvePositionIndicator

-LimitSwitchesSafetyValvePositionIndicator

-AcousticMonitorIncoreThermocouples (CoreExitThermocouples)

ReactorCoolantInventory TrackingSystem(ReactorVesselLevelIndication)

Containment SumpLevelContainment WaterLevel222222/steamgenerator 1/steamgenerator 211/steamgenerator*

1**1/Valve1/Valve1/Valve2/CoreQuadrantOneTrain(3Channels/Train) 12*SteamGenerator WaterLevelChannelscanbeusedasasubstitute forthecorresponding auxiliary feedwater flowratechannelinstrument.

PPCsubcooling marginreadoutcanbeusedasasubstitute forthesubcooling monitorinstrument.

Acousticmonitoring ofPORVposition(1channelperthreevalves-headereddischarge) canbeusedasasubstitute forthePORVPositionIndicator

-LimitSwitchesinstruments.

COOKNUCLEARPLANT-UNIT13/43-55Amendment No.~,4k&,46k,468 TABLE43-POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REUIREMENTS INSTRUMENT CHANNELCHECKCHANNELCALIBRATION 1.Containment Pressure2.ReactorCoolantOutletTemperature-THOT(WideRange)3.ReactorCoolantInletTemperature-TCO(WideRange)4.ReaRcorCoolantPressure-Wide Range5.Pressurizer WaterLevel6.SteamLinePressure7,SteamGenerator WaterLevel-Narrow Range8~RWSTWaterLevel9.BoricAcidTankSolutionLevel10.Auxiliary Feedwater FlowRate11.Reactor CoolantSystemSubcooling MarginMonitor12.PORVPositionIndicator

-LimitSwitches13.PORVBlockValvePositionIndicator-LimitSwitches14.Safety ValvePositionIndicator-AcousticMonitor15.Incore Thermocouples (CoreExitThermocouples) 16.Reactor CoolantInventory TrackingSystem(ReactorVesselLevelIndication) 17.Containment SumpLevel18.Containment WaterLevelMMMMMMMMMMMMM(2)MMRRRRRRRRRRRR(1)R(3)RR(1)Partialrangechannelcalibration forsensortobeperformed belowP-12inMODE3.(2)WithonetrainofReactorVesselLevelIndication inoperable, Subcooling MarginIndication andCoreExitThermocouples maybeusedtoperformaCHANNELCHECKtoverifytheremaining ReactorVesselIndication trainOPERABLE.

(3)Completion ofchannelcalibration forsensorstobeperformed belowP-12inMODE3.COOKNUCLEARPLANT-UNIT13/43-56AMENDMENT NO.54)444 TABLE3.7-6LOWPRESSURECARBONDIOXIDESYSTEMSLOCATIONACTUATION PERIODDieselGenerator 1ABRoomDieselGenerator 1CDRoomDieselGenerator FuelOilPumpRoom4KVSwitchgear RoomsControlRodDrive,Transf.Switchgear RoomsEngineered SafetySwitchgear RoomSwitchgear RoomCableVaultCross-zoned HeatCross-zoned HeatHeatManualManualManualCross-zoned Ionization andInfraredAuxiliary CableVaultControlRoomCableVault(Backup)*

Penetration CableTunnelQuadrant1Penetration CableTunnelQuadrant2Penetration CableTunnelQuadrant3NPenetration CableTunnelQuadrant3MPenetration CableTunnelQuadrant3SPenetration CableTunnelQuadrant4Ionization ManualManualManualManualManualManualManual*ControlRoomCableVaultCO>SystemisonlyrequiredtobeoperablewhentheCableVaultHalonSystemisinoperable.

COOKNUCLEARPLANT-UNIT13/47;41AMENDMENT NO.M,430, REFUELING OPERATIONS CRANETRAVEL-SPENTFUELSTORAGEPOOLBUILDING*

LIMITINGCONDITION FOROPERATION 3.9.7Loadsinexcessof2,500poundsshallbeprohibited fromtraveloverfuelassemblies inthestoragepool.Loadscarriedoverthespentfuelpoolandtheheightsatwhichtheymaybecarriedoverrackscontaining fuelshallbelimitedinsuchawayastoprecludeimpactenergiesover24,240in.-lbs.,

iftheloadsaredroppedfromthecrane.APPLICABILITY:

Withfuelassemblies inthestoragepool.~GTION:Withtherequirements oftheabovespecification notsatisfied, placethecraneloadinasafecondition.

Theprovisions ofSpecification 3.0.3arenotapplicable.

SURVEILLANCE REUIREMENTS 4.9.7.1Craneinterlocks whichpreventcranetravelwithloadsin'excessof2,500poundsoverfuelassemblies shallbedemonstrated OPERABLEwithin7dayspriortocraneuseandatleastonceper7daysthereafter duringcraneoperation.

4.9.7.2Thepotential impactenergyduetodroppingthecrane'sloadshallbedetermined tobes24,240in.-lbs.priortomovingeachloadoverrackscontaining fuel.*SharedsystemwithCookNuclearPlant-Unit2.COOKNUCLEARPLANT-UNIT13/49-8AMENDMENT NO.

P~~

RADIOACTIVE EFFLUENTS GASEOUSRADWASTETREATMENT LIMITINGCONDITION FOROPERATION 3.11.2.4Thegaseousradwastetreatment systemandtheventilation exhausttreatment systemshallbeusedtoreducetheradioactive materials ingaseouswastepriortotheirdischaige whentheprojected gaseouseffluentairdosesduetogaseouseffluentreleasestounrestricted areas(geeFigure5.1-3)whenaveragedover31days,wouldexceed0.2mradforgammaradiation and0.4mradforbetaradiation.

Theventilation exhausttreatment systemshallbeusedtoreduceradioactive materials ingaseouswastepriortotheirdischarge whentheprojected dosesduetogaseouseffluentreleasestounrestricted areas(SeeFigure5.1-3)whenaveragedover31dayswouldexceed0.3mremtoanyorgan.APPLICABILITY:

Atalltimes.ACTION:a.Withgaseouswastebeingdischarged withouttreatment andinexcessoftheabovelimits,prepareandsubmittotheCommission within30days,pursuanttoSpecification 6.9.2,aSpecialReportwhichincludesthefollowing information:

1.Identification oftheinoperable equipment orsubsystems andthereasonforinoperability.

2.Action(s) takentorestoretheinoperable equipment tooperablestatus.b.Theprovisions ofSpecifications 3.0.3and3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.11.2.4DosesduetogaseousreleasestoUNRESTRICTED AREASshallbeprojected atleastonceper31daysinaccordance withtheODCM,wheneverthegaseouswastetreatment systemorventilation exhausttreatment systemisnotoperational.

COOKNUCLEARPLANT-UNIT13/411-12AMENDMENT NO.60,454 fr,~r"STATEOFMICHIGANSCALE1:2400035'IMILEKALAaf47QO$0aff6rffl.TO(g,s33300001CO2000300040005000.S0)KIEOMDER.Lakes/36Qj(~i6~~~Errr'.~~a./':/~"~~-'I>>'f:I('averland Beach/'~~'-'i'MTSSTSS5~MP0:.f60I14'-6a0Ir0O'Vf//fff.6IO~O:0g~~OIO,".)rCV~~f~RosemaryBeachO~i.p/faerfcorrfr~L'f'i~~,~vent6j'~'rrfff"'rd'A(r!g66/~4Livingston

'//~Op0'-;~>~Omn,

.'-,.-.,i'/:/q-

".;4~~~tV'ri'./,//j't/ji".

/r,gjforrNuclearPlantExclusion Area~fl'.Landinsrstfip Figure5.1-1,i"-"DorlhldC."Cookgrf0i667f~CRE'EKCOOKNUCLEARPLANT-UNIT1 DESIGNFEATURESCAPACITY5.6.4Thefuelstoragepoolisdesignedandshallbemaintained withastoragecapacitylimitedtonomorethan3613fuelassemblies.

57SEISMICCLASSIFICATION 5.7.1Thosestructures, systemsandcomponents identified asCategoryIItemsintheFSARshallbedesignedandmaintained totheoriginaldesignprovisions contained intheFSARwithallowance fornormaldegradation pursuanttotheapplicant Surveillance Requirements.

58METEROLOGICAL TOWERLOCATION5.8.1Themeterological towershallbelocatedasshownonFigure5.1-3.59COMPONENT CYCLICORTRANSIENT LIMIT5.9.1Thecomponents identified inTable5.9-1aredesignedandshallbemaintained withinthecyclicortransient limitsofTable5.9-1.COOKNUCLEARPLANT-UNIT15-9AMENDMENT NO.40>

LI ADMINISTRATIVE CONTROLS61RESPONSIBILITY 6.1.1ThePlantManagershallberesponsible foroverallfacilityoperation andshalldelegateinwritingthesuccession tothisresponsibility duringhisabsence.6.1.2TheShiftSupervisor (orduringhisabsencefromthecontrolroomcomplex,adesignated individual) shallberesponsible forthecontrolroomcommandfunction.

Amanagement directive tothiseffectsignedbytheVicePresident

-NuclearOperations shallbereissuedtoallstationpersonnel onanannualbasis.62ORGANIZATION ONSITEANDOFFSITEORGANIZATIONS 6.2.1Onsiteandoffsiteorganizations shallbeestablished forunitoperation andcorporate management, respectively.

Theonsiteandoffsiteorganizations shallincludethepositions foractivities affecting thesafetyofthenuclearpowerplant.a.Linesofauthority, responsibility, andcommunication shallbeestablished anddefinedforthehighestmanagement levelthroughintermediate levelstoandincluding alloperating organization positions.

Theserelationships shallbedocumented andupdated,asappropriate, intheformoforganizational charts.Theseorganizational chartswillbedocumented intheUFSARandupdatedinaccordance with10CFR50.71(e).

b.ThePlantManagershallberesponsible foroverallunitsafeoperation andshallhavecontroloverthoseonsiteactivities necessary forsafeoperation andmaintenance oftheplant.cod.'heVicePresident

-NuclearOperations shallhavecorporate responsibility foroverallplantnuclearsafetyandshalltakeanymeasuresneededtoensureacceptable performance ofthestaffinoperating, maintaining, andproviding technical supporttotheplanttoensurenuclearsafety.Theindividuals whotraintheoperating staffandthosewhocarryouthealthphysicsandqualityassurance functions mayreporttotheappropriate onsitemanager;however,theyshallhavesufficient organizational freedomtoensuretheirindependence fromoperating pressures.

FACILITYSTAFF6.2.2TheFacilityorganization shallbesubjecttothefollowing:

a.Eachonduty,shiftshallbecomposedofatleasttheminimumshiftcrewcomposition showninTable6.2-1.COOKNUCLEARPLANT-UNIT16-1AMENDMENT NO.

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 mustholdorhaveheldaSeniorOperatorLicenseasspecified inSection6.2.2.h.6.4TRAINING6.4.1Aretraining andreplacement trainingprogramforthefacilitystaffshallbemaintained underthedirection oftheTrainingManagerandshallmeetorexceedtherequirements andrecommendations ofSection5.5ofANSIN18.1-1971 and10CFRPart55.65REVIEWANDAUDIT6.51PLANTNUCLEARSAFETYREVIEWCOMMITTEE PNSRCFUNCTION6.5.1.1ThePNSRCshallfunctiontoadvisethePlantManageronallmattersrelatedtonuclearsafety.COMPOSITION 6.5.1.2ThePNSRCshallbecomposedofAssistant PlantManagers, Department Superintendents, orsupervisory personnel reporting directlytothePlantManager,Assistant PlantManagersorDepartment Superintendents fromthefunctional areaslistedbelow:Licensing Activities Safety&Assessment Operations Technical SupportRadiation Protection Maintenance TheChairman, hisalternate andothermembersandtheiralternates ofthePNSRCshallbedesignated bythePlantManager.InadditiontotheChairman, thePNSRCmembership shallconsistofoneindividual fromeachoftheareasdesignated above.PNSRCmembersandalternates shallmeetorexceedtheminimumqualifications ofANSIN18.1-1971 Section4.4forcomparable positions.

Thenuclearpowerplantoperations individual shallme'etthequalifications ofSection4.2.2ofANSIN18.1-1971 exceptfortherequirement toholdacurrentSeniorOperatorLicense.Theoperations individual mustholdorhaveheldaSeniorOperatorLicenseatCookNuclearPlantorasimilarreactor.Themaintenance individual shallmeetthequalifications ofSection4:2.3ofANSIN18.1-1971.

COOKNUCLEARPLANT-UNIT16-4AMENDMENT NO.49,

INSTRUMENTATION BASES34335REMOTESHUTDOWNINSTRUMENTATION TheOPERABILITY oftheremoteshutdowninstrumentation ensuresthatsufficient capability isavailable topermitshutdownandmaintenance ofHOTSTANDBYofthefacilityfromlocations outsideofthecontrolroom.Thiscapability isrequiredintheeventcontrolroomhabitability islostandisconsistent withGeneralDesignCriteria19of10CFR50.343351APPENDIXRREMOTESHUTDOWNINSTRUMENTATION TheOPERABILITY oftheAppendixRremoteshutdowninstrumentation ensuresthatsufficient instrumentation isavailable topermitshutdownofthefacilitytoCOLDSHUTDOWNconditions atthelocalshutdownindication (LSI)panel.Intheeventofafire,normalpowertotheLSIpanelsmaybelost.Asaresult,capability torepairtheLSIpanelsfromUnit2hasbeenprovided.

Ifthealternate powersupplyisnotavailable, firewatcheswillbeestablished inthosefireareaswherelossofnormalpowertotheLSIpanelscouldoccurintheeventoffire.Thiswillconsistofeitherestablishing continuous firewatchesorverifying OPERABILITY offiredetectors perSpecification 4.3.3.7andestablishing hourlyfirewatches.Thedetailsofhowthesefirewatchesaretobeimplemented areincludedinaplantprocedure.

3433FIREDETECTION INSTRUMENTATION SYSTEMSDETECTORS OPERABILITY ofthefiredetection systems/detectors ensuresthatadequatedetection capability isavailable forthepromptdetection offires.Thiscapability isrequiredinordertodetectandlocatefiresintheirearlystages.Promptdetection ofthefireswillreducethepotential fordamagetosafetyrelatedsystemsorcomponents intheareasofthespecified systemsandisanintegralelementintheoverallfacilityfireprotection program.Intheeventthataportionofthefiredetection systemsisinoperable, theACTIONstatements providedmaintainthefacility's fireprotection programandallowsforcontinued operation ofthefacilityuntiltheinoperable system(s)/detector(s) arerestoredtoOPERABILITY.

However,itisnotourintenttorelyuponthecompensatory actionforanextendedperiodoftimeandactionwillbetakentorestoretheminimumnumberofdetectors toOPERABLEstatuswithinareasonable period.34338POST-ACCIDENT INSTRUMENTATION TheOPERABILITY ofthepost-accident instrumentation ensuresthatsufficient information isavailable onselectedplantparameters tomonitorandassessthesevariables duringandfollowing anaccident.

COOKNUCLEARPLANT-UNIT1B3/43-6AMENDMENT NO.

REFUELING OPERATIONS BASES34910and349llWATERLEVEL-REACTORVESSELANDSTORAGEPOOLTherestrictions onminimumwaterlevelensurethatsufficient waterdepthisavailable toremove99%oftheassumed10$iodinegapactivityreleasedfromtheruptureofanirradiated fuelassembly.

Theminimumwaterdepthisconsistent withtheassumptions oftheaccidentanalysis, WaterlevelabovethevesselflangeinMODE6willvaryasthereactorvesselheadandthesysteminternals areremoved.The23feetofwaterarerequiredbeforeanysubsequent movementoffuelassemblies orcontrolrods.34912STORAGEPOOLVENTILATION SYSTEMThelimitations onthestoragepoolventilation systemensurethatallradioactive materialreleasedfromanirradiated fuelassemblywillbefilteredthroughtheHEPAfiltersandcharcoaladsorberpriortodischarge totheatmosphere.

TheOPERABILITY ofthissystemandtheresulting iodineremovalcapacityareconsistent withtheassumptions oftheaccidentanalyses.

The1980versionofANSIN510isusedasatestingguide.Thisstandard, however,isintendedtoberigorously appliedonlytosystemswhich,unlikethestoragepoolventilation system,aredesignedtoANSIN509standards.

Forthespecificcaseoftheair-aerosol mixinguniformity testrequiredbyANSIN510asaprerequisite toin-placeleaktestingofcharcoalandHEPAfilters,theair-aerosol uniformmixingtestacceptance criteriawerenotrigorously met.Forthisreason,astatistical correction factorwillbeappliedtoapplicable surveillance testresultswhererequired.

InordertomaintaintheminimumnegativepressurerequiredbyTechnical Specifications (1/8inchW.G.)duringmovementoffuelwithinthestoragepoolorduringcraneoperation withloadsoverthepool,thecranebayroll-updoorandthedrummingroomroll-updoor,locatedonthe609-footelevation oftheauxiliary

building, mustbeclosed.However,theymaybeopenedduringtheseoperations underadministrative control.Ifthecranebaydoorneedstobeopenedduringfuelmovement, anexampleofanadministrative controlmightbetostationanindividual atthedoorwhowouldbeincommunication withpersonnel inthespentfuelpoolareaandcouldclosethedoorwhenpassagethroughthedoorwascompleted orintheeventofanemergency.

Forthedrummingroomdoor,anexampleofanadministrative controlmightbetorequirethedoortobereclosedafternormalingressandegressofpersonnel ormaterial, ortostationanindividual atthedoorifthedoorneedstoremainopenforanextendedperiodoftime.Shouldthedoorsbecomeblockedorstuckopenwhileunderadministrative control,Technical Specification requirements willnotbeconsidered tobeviolatedprovidedtheActionStatement requirements ofSpecification 3.9.12areexpeditiously

followed, i.e.,movementoffuelwithinthestoragepoolorcraneoperation withloadsoverthepoolisexpeditiously suspended.

COOKNUCLEARPLANT-UNIT1B3/49-3AMENDMENT NO.

TABLE3.3-1Continued REACTORTRIPSYSTEMINSTRUMENTATION FUNCTIONAL UNIT16.Undervoltage-Reactor CoolantPumpsTOTALNO.OFCHANNELS4-1/busCHANNELSTOTRIPMINIMUMCHANNELSOPERABLEAPPLICABLE MODES17.Underfrecpxency-Reactor 4-1/busCoolantPumps18.TurbineTripA.LowFluidOilPressureB.TurbineStopValveClosure19.SafetyInjection InputfromESF1I220.'ReactorCoolantPumpBreakerPositionTripAboveP-721.ReactorTripBreakers1/breaker 1/breaker peroperating loop1I2/3*4*5*1331422.Automatic TripLogic1I2I3*4*5*114COOKNUCLEARPLANT-UNIT23/43-4AMENDMENT

NO86,

~TABLE33-1Continued DESIGNATION CONDITION ANDSETPOINTFUNCTIONP-7With2of4PowerRangeNeutronFluxChannels~11$ofRATEDTHERMALPOWERor1of2PressurebeforetheFirstStagechannels~51psig.P-7preventsordefeatstheautomatic blockofreactortripon:Lowflowinmorethanoneprimarycoolantloop,reactorcoolantpumpunder-voltage andunder-frequency, turbinetrip,pressurizer lowpressure, andpressurizer highlevel.Lowflowinaparticular loopcanbeevidenced byeitheradetectedlowfloworbytheopeningofthereactorcoolantpumpbreaker.P-8With2of4PowerRangeNeutronFluxchannelsE31%ofRATEDTHERMALPOWER.P-8preventsordefeatstheautomatic blockofreactortripcausedbyalowcoolantflowcondition inasingleloop.P-10With3of4PowerRangeNeutronfluxchannels<9%ofRATEDTHERMALPOWER..P-10preventsordefeatsthemanualblockof:Powerrangelowsetpointreactortrip,Inter-mediaterangereactortrip,andintermediate rangerodstops.ProvidesinputtoP-7.COOKNUCLEARPLANT-UNIT23/43-8AMENDMENT NO.

TABLE3.3-10POST-ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUMCHANNELSOPERABLE1~2~3~4~5.6.7~8.9~10.11.12.13~14.15.16.17.18.Containment PressureReactorCoolantOutletTemperature

-THpT(WideRange)ReactorCoolantInletTemperature

-Tp~i~(WideRange)ReactorCoolantPressure-WideRangePressurizer WaterLevelSteamLinePressureSteamGenerator WaterLevel-NarrowRangeRefueling WaterStorageTankWaterLevelBoricAcidTankSolutionLevelAuxiliary Feedwater FlowRateReactorCoolantSystemsubcooling MarginMonitorPORVPositionIndicator

-LimitSwitches***

PORVBlockValvePositionIndicator

-LimitSwitches,SafetyValvePositionIndicator

-AcousticMonitorIncoreThermocouples (CoreExitThermocouples)

ReactorCoolantInventory TrackingSystem(ReactorVesselLevelIndication)

Containment SumpLevelContainment WaterLevel222222/SteamGenerator 1/SteamGenerator 211/SteamGenerator*

]**1/Valve1/Valve1/Valve2/CoreQuadrantOneTrain'(3Channels/Train) 12*SteamGenerator WaterLevelChannelscanbeusedasasubstitute forthecorresponding auxiliary feedwater flowratechannelinstrument.

PPCsubcooling marginreadoutcanbeusedasasubstitute forthesubcooling monitorinstrument.

Acousticmonitoring ofPORVposition(1channelperthreevalves-headereddischarge) canbeusedasasubstitute forthePORVIndicator

-LimitSwitchesinstruments.

1COOKNUCLEARPLANT-UNIT23/43-46Amendment.

No.9&,9S,~,~

TABLE4.3-10POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REUIREMENTS CHANNELCHECKCHANNELCAIZHfQTION 1~2~3~4~5.6.7~8~9~10.1112.13.14.15.16'7~18~Containment PressureReactorCoolantOutletTemperature

-T~~(WideRange)ReactorCoolantInletTemperature

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

-LimitSwitchesPORVBlockValvePositionIndicator

-LimitSwitchesSafetyValvePositionIndicator

-AcousticMonitorIncoreThermocouples (CoreExitThermocouples)

ReactorCoolantInventory TrackingSystem(ReactorVesselLevelIndication)

Containment SumpLevelContainment WaterLevelMMMMMMMMMMMMMMMM(2)MMRRRRRRRRRRRRRRR(1)R(3)RR(2)(3)Partialrangechannelcalibration forsensortobeperformed belowP-12inMODE3.WithonetrainofReactorVesselLevelIndication inoperable, Subcooling MarginIndication andCoreExitThermocouples maybeusedtoperformaCHANNELCHECKtoverifytheremaining ReactorVesselIndication trainOPERABLE.

Completion ofchannelcalibration forsensorstobeperformed belowP-12inMODE3.COOKNUCLEARPLANT-UNIT23/43-47AMENDMENT NO.9&,9S, TABLE33-11Unit2andCommonAreaFireDetection SstemsDetection SstemLocationAuxiliary Buildinga)Elevation 573b)Elevation 587c)Elevation 609d)Elevation 633e)Elevation 650f)NewFuelSTGEAreaHeat(x/y)*TotalNumberofDetectors

~lame(x/y)*Smoke(x/y)*23/0C55/0C41/0C41/0C34/0C4/0CU2EastMainSteamValveEnclosure U2MainSteamLineAreaEl.612(AroundContainment)

U2NESWValveAreaEl.612U24KVSwitchgear (AB)U24KVSwitchgear (CD)U2Engr.SafetySystemSwitchgear

&XFMR.Rm.U2CRD,XFMR&Switchgear Rm.Inverter6ABBttry.Rms.0/30/30/50/528/0**13/0**2/00/20/20/140/17U2Pressurizer HeaterXFMR.Rm.U2DieselFuelOilTransferPumpRm.0/1U2DieselGenerator Rm.2AB0/2U2DieselGenerator Rm.2CD0/2U2DieselGenerator RampCorr.Ul&2AFWPVestibule 12/04/02/0CU2ControlRoomU2Switchgear CableVaultU2ControlRm.CableVaultU2Aux.CableVaultUl&2ESWBasementAreaU2ESWPump&MCCRms.42/00/10*~0/130/76*%%*0/64/0C9/0CSystemprotectsareacommontobothUnits1and2*(x/y)xisnumberofFunctionA(earlywarningfiredetection andnotification only)instruments..

yisnumberofFunct:ion B'(actuation offiresuppression systemsand'arlywarningandnotification) instruments.

circuitcontainsbothsmokeandflamedetectors

• • • twocircuit:s offivedetectors each~**twocircuitsof38detectors eachCOOKNUCLEARPLANT-UNIT23/43-52AMENDMENT NO.44,

REFUELING OPERATIONS CRANETRAVEL-SPENTFUELSTORAGEPOOLBUILDING*

LIMITINGCONDITION FOROPERATION 3.9.7Loadsinexcessof2,500poundsshallbeprohibited fromtraveloverfuelassemblies inthestoragepool.Loadscarriedoverthespentfuelpoolandtheheightsatwhich'hey maybecarriedoverrackscontaining fuelshallbelimitedinsuchawayastoprecludeimpactenergiesover24,240in.-lbs.,

iftheloadsaredroppedfromthecrane.APPLICABILITY:

Withfuelassemblies inthestoragepool.ACTION:Withtherequirements oftheabovespecification notsatisfied, placethecraneloadinasafecondition.

Theprovisions ofSpecification 3.0.3arenotapplicable.

SVEILLANCE REUIREMENTS 4.9.7.1Craneinterlocks whichpreventcranetravelwithloadsinexcessof2,500poundsoverfuelassemblies shallbedemonstrated OPERABLEwithin7dayspriortocraneuseandatleastonceper7daysthereafter duringcraneoperation.

4.9.7.2Thepotential impactenergyduetodroppingthecrane'sloadshallbedetermined tobes24,240in.-lbs.priortomovingeachloadoverrackscontaining fuel.*SharedsystemwithCookNuclearPlant-Unit1.COOKNUCLEARPLANT-UNIT23/49-7AMENDMENT NO.M,96

~~~REFUELING OPERATIONS SURVEILLANCE REUIREMENTS Continued 3.Verifying thattheHEPAfilterbanksremovegreaterthanorequalto99%oftheDOPwhentheyaretestedin-placeinaccordance withANSIN510-1980 whileoperating theexhaustventilation systemataflowrateof30,000cfmplusorminus108.4.Verifying within31daysafterremovalthatalaboratory analysisofacarbonsamplefromeitheratleastonetestcanisteroratleasttwocarbonsamplesremovedfromoneofthecharcoaladsorbers demonstrates aremovalefficiency ofgreaterthanorequalto90$forradioactive methyliodidewhenthesampleistestedinaccordance withANSIN510-1980 (ASTMD3803-1979, 30C,95%R.H.).Thecarbonsamplesnotobtainedfromtestcanisters shallbepreparedbyeither:(a)Emptyingoneentirebedfromaremovedadsorbertray,mixingtheadsorbent thoroughly, andobtaining samplesatleasttwoinchesindiameterandwithalengthequaltothethickness ofthebed,or(b)Emptyingalongitudinal samplefromanadsorbertray,mixingtheadsorbent thoroughly, andobtaining samplesatleasttwoinchesindiameterandwithalengthequaltothethickness ofthebed.Subsequent toreinstalling theadsorbertrayusedforobtaining thecarbonsample,thesystemshallbedemonstrated OPERABLEbyalsoverifying thatthecharcoaladsorbers removegreaterthanorequalto99%ofahalogenated hydrocarbon refrigerant testgaswhentheyaretestedin-placeinaccordance withANSIN510-1980 whileoperating theventilation systemataflowrateof30,000cfmplusorminus10%.5.Verifying asystemflowrateof30,000cfmplusorminus108duringsystemoperation whentestedinaccordance withANSIN510-1980.

C.Afterevery720hoursofcharcoaladsorberoperation byeither:1.Verifying within31daysafterremovalthatalaboratory analysisofacarbonsampleobtainedfromatestcanisterdemonstrates aremovalefficiency ofgreaterthanorequalto90$forradioactive methyliodidewhenthesampleis'estedinaccordance withANSIN510-1980 (ASTMD3803-1979, 30C,95',R.H.).

COOKNUCLEARPLANT-UNIT23/49-13AMENDMENT NO.~,440 RADIOACTIVE EFFLUENTS GASEOUSRADWASTETREATMENT LIMITINGCONDITION FOROPERATION 3.11.2.4Thegaseousradwastetreatment systemandtheventilation exhausttreatment systemshallbeusedtoreducetheradioactive materials ingaseouswastepriortotheirdischarge whentheprojected gaseouseffluentairdosesduetogaseouseffluentreleasestounrestricted areas(SeeFigure5.1-3)whenaveragedover31days,wouldexceed0.2mradforgammaradiation and0.4mrad.forbetaradiation.

Theventilation exhausttreatment systemshallbeusedtoreduceradioactive materials ingaseouswastepriortotheirdischarge whentheprojected dosesduetogaseouseffluentreleasestounrestricted areas(SeeFigure5.1-3)whenaveragedover31dayswouldexceed0.3mremtoanyorgan.APPLICABILITY:

Atalltimes.ACTION'.Withgaseouswastebeingdischarged withouttreatment andinexcessoftheabovelimits,prepareandsubmittotheCommission within30days,pursuanttoSpecification 6.9.2,aSpecialReportwhichincludesthefollowing information:

1.Identification oftheinoperable equipment orsubsystems andthereasonforinoperability.

2~Action(s) takentorestoretheinoperable equipment tooperablestatus.b.Theprovisions ofSpecifications 3.0.3and3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.11'.4DosesduetogaseousreleasestoUNRESTRICTED AREASshallbeprojected atleastonceper31daysinaccordance withtheODCM,wheneverthegaseouswastetreatment systemorventilation exhausttreatment systemisnotoperational.

COOKNUCLEARPLANT-UNIT23/411-12AMENDMENT NO.M,438

C~AC~4SvVOLUME5.4.2Thetotalwaterandsteamvolumeofthereactorcoolantsystemis12,612plusorminus100cubicfeetatanominalTavgof70F.5.5METEOROLOGICAL TOWERLOCATIONThemeteorological towershallbelocatedasshownonFigure5.1-3.Bl-CRITICALITY

-SPENTFUEL5.6.1.1Thespentfuelstorageracksaredesignedandshallbemaintained with:a.AK,qqequivalent tolessthan0.95whenfloodedwithunborated water,b.Anominal8.97-inch center-to-center distancebetweenfuelassemblies, placedinthestorageracks.c~Thefuelassemblies willbeclassified asacceptable forRegion1,Region2,orRegion3storagebasedupontheirassemblyburnupversusinitialnominalenrichment.

Cellsacceptable forRegion1,Region2,andRegion3assemblystorageareindicated inFigures5.6-1and5.6-2.Assemblies thatareacceptable forstorageinRegion1,Region2,andRegion3mustmeetthedesigncriteriathatdefinetheregionsasfollows:1.Region1isdesignedtoaccommodate newfuelwithamaximumnominalenrichment of4.95wtSU-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.

COOKNUCLEARPLANT-UNIT25-5AMENDMENT NO.55,404, DMINISTRATIVE CONTROLS61RESPONSIBILITY 6.1.1ThePlantManagershallberesponsible foroverallfacilityoperation andshalldelegateinwritingthesuccession tothisresponsibility duringhisabsence.6.1.2TheShiftSupervisor (orduringhisabsencefromthecontrolroomcomplex,adesignated individual) shallberesponsible forthecontrolroomcommandfunction.

Amanagement directive tothiseffectsignedbytheVicePresident

-NuclearOperations shallbereissuedtoallstationpersonnel onanannualbasis.62ORGANIZATION ONSITEANDOFFSITEORGANIZATIONS 6.2.1Onsiteandoffsiteorganizations shallbeestablished forunitoperation andcorporate management, respectively.

Theonsiteandoffsiteorganizations shallincludethepositions foractivities affecting thesafetyofthenuclearpowerplant.a.Linesofauthority, responsibility, andcommunication shallbeestablished anddefinedforthehighestmanagement levelthroughintermediate levelstoandincluding alloperating organization positions.

Theserelationships shallbedocumented andupdated,asappropriate, intheformoforganizational charts.Theseorganizational chartswillbedocumented intheUFSARandupdatedinaccordance with10CFR50.71(e).

b.ThePlantManagershallberesponsible foroverallunitsafeoperation andshallhavecontroloverthoseonsiteactivities necessary forsafeoperation andmaintenance oftheplant.C.TheVicePresident

-NuclearOperations shallhavecorporate responsibility foroverallplantnuclearsafetyandshalltakeanymeasuresneededtoensureacceptable performance ofthestaffinoperating, maintaining, andpioviding technical supporttotheplanttoensurenuclearsafety.d.Theindividuals whotrainthedperating staffandthosewhocarryouthealthphysicsandqualityassurance functions mayreporttotheappropriate onsitemanager;'owever, they'shallhavesufficient organizational freedomtoensuretheirindependence fromoperating pressures.

FACILITYSTAFF6.2.2TheFacilityorganization shallbesubjecttothefollowing:

a.Eachondutyshiftshallbecomposedofatleasttheminimumshiftcrewcomposition shownin-Table6.2-1.COOKNUCLEARPLANT-UNIT26-1AMENDMENT NO.58, ADMINISTRATIVE CONTROLS63FACILITYSTAFFUALIFICATIONS 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, whomustholdorhaveheldaSeniorOperatorLicenseasspecified inSection6.2.2.h.64TRAINING6.4.1Aretraining andreplacement trainingprogramforthefacilitystaffshallbemaintained underthedirection oftheTrainingManagerandshallmeetorexceedtherequirements andrecommendations ofSection5.5ofANSIN18.1-1971 and10CFRPart55.65REVIEWANDAUDIT651PLANTNUCLEARSAFETYREVIEWCOMMITTEE PNSRCFUNCTION6.5.1.1ThePNSRCshallfunctiontoadvisethePlantManageronallmattersrelatedtonuclearsafety.COMPOSITION 6.5.1.2ThePNSRCshallbecomposedofAssistant PlantManagers, Department Superintendents, orsupervisory personnel reporting directlytothePlantManager,Assistant PlantManagersorDepartment Superintendents fromthefunctional areaslistedbelow:Licensing Activities Safety&Assessment Operations Technical SupportRadiation Protection Maintenance TheChairman, hisalternate andothermembersandtheiralternates of,thePNSRCshallbedesignated bythePlantManager.InadditiontotheChairman, thePNSRCmembership shallconsistofoneindividual fromeachoftheareasdesignated above,PNSRCmembersandalternates shallmeetorexceedtheminimumqualifications ofANSIN18.1-1971 Section4.4forcomparable positions.

Thenuclearpowerplantoperations individual shallmeetthequalifications ofSection4.2.2ofANSIN18.1-1971 exceptfortherequirement toholdacurrentSeniorOperatorLicense.Theoperations individual mustholdorhaveheldaSeniorOperatorLicenseatCookNuclearPlantorasimilarreactor.Themaintenance individual shallmeetthequalifications ofSection4.2.3ofANSIN18.1-1971..

COOKNUCLEARPLANT-UNIT26-4AMENDMENT NO.

INSTRUMENTATION BASES34336POST-ACCIDENT INSTRUMENTATION TheOPERABILITY ofthepost-accident instrumentation ensuresthatsufficient information isavailable onselectedplantparameters tomonitorandassessthesevariables duringandfollowing anaccident.

3433DELETED34338FIREDETECTION INSTRUMENTATION OPERABILITY ofthefiredetection instrumentation ensuresthatadequatewarningcapability isavailable for,thepromptdetection offires.Thiscapability isrequiredinordertodetectandlocatefiresintheirearlystages.Promptdetection offireswillreducethepotential fordamagetosafety-related equipment andisanintegralelementintheoverallfacilityfireprotection program.Intheeventthataportionofthefiredetection instrumentation isinoperable, theestablishment offrequentfirepatrolsintheaffectedareasisrequiredtoprovidedetection capability untiltheinoperable instrumentation isrestoredtoOPERABILITY.

Useofcontainment temperature monitoring isallowedonceperhourifcontainment firedetection isinoperable.

34339RADIOACTIVE LIUIDEFFLUENTINSTRUMENTATION Theradioactive liquideffluentinstrumentation isprovidedtomonitorandcontrol,asapplicable, thereleaseofradioactive materialinliquideffluents duringactualorpotential releases.

Thealarm/trip setpoints fortheseinstruments shallbecalculated inaccordance withNRCapprovalmethodsintheODCMtoensurethatthealarm/trip willoccurpriortoexceeding thelimitsof10CFRPart20.TheOPERABILITY anduseofthisinstrumentation isconsistent withtherequirements ofGeneralDesignCriteriaspecified inSection11.3oftheFinalSafetyAnalysisReportfortheDonaldC.CookNuclearPlant.COOKNUCLEARPLANT-UNIT2B3/43-3AMENDMENT NO.44, REFUELING OPERATIONS BASES3499CONTAINMENT PURGEANDEXHAUSTISOLATION SYSTEMTheOPERABILITY ofthissystemensuresthatthecontainment ventandpurgepenetrations willbeautomatically isolatedupondetection ofhighradiation levelswithinthecontainment.

TheOPERABILITY ofthissystemisrequiredtorestrictthereleaseofradioactive materialfromthecontainment atmosphere totheenvironment.

34910AND34911WATERLEVEL-REACTORVESSELANDSTORAGEPOOTherestrictions onminimumwaterlevelensurethatsufficient waterdepthisavailable toremove99%oftheassumed10%iodinegapactivityreleasedfromtheruptureofanirradiated fuelassembly.

Theminimumwaterdepthisconsistent withtheassumptions oftheaccidentanalysis.

WaterlevelabovethevesselflangeinMODE6will.,vary asthereactorvesselheadandthesysteminternals areremoved.The23feetofwaterarerequiredbeforeanysubsequent movementoffuelassemblies orcontrolrods.34912STORAGEPOOLVENTILATION SYSTEMThelimitations onthestoragepoolventilation systemensurethatallradioactive materialreleasedfromanirradiated fuelassemblywillbefilteredthroughtheHEPAfiltersandcharcoaladsorberpriortodischarge totheatmosphere.

TheOPERABILITY ofthissystemandtheresulting iodineremovalcapacityareconsistent withtheassumptions oftheaccidentanalyses.

The1980versionofANSIN510isusedasatestingguide.Thisstandard, however,isintendedtoberigorously appliedonlytosystemswhich,unlikethestoragepoolventilation system,aredesignedtoANSIN509standards, Forthespecificcaseoftheair-aerosol mixinguniformity testrequiredbyANSIN510asaprerequisite toin-placeleaktestingofcharcoalandHEPAfilters,theair-aerosol uniformmixingtestacceptance criteria.werenotrigorously met.Forthisreason,astatistical correction factorwillbeappliedtoapplicable surveillance testresultswhererequired.

InordertomaintaintheminimumnegativepressurerequiredbyTechnical Specifications (1/8inchW.G.)duringmovementoffuelwithinthestoragepoolorduringcraneoperation withloadsoverthepool,thecranebayroll-updoorandthedrummingroomroll-updoor,locatedonthe609-footelevation oftheauxiliary

building, mustbeclosed.However,theymaybeopenedduringtheseoperations underadministrative control.Ifthecranebaydoorneedstobeopenedduringfuelmovement, anexampleofanadministrative controlmightbetostationanindividual atthedoorwhowouldbeincommunication withpersonnel inthespentfuelpoolareaandcouldclosethedoorwhenpassagethroughthedoorwascompleted orintheeventofanemergency.

Forthedrummingroomdoor,anexampleofanadministrative controlmightbetorequirethedoortobereclosedafternormalingressandegressofpersonnel ormaterial, ortostationanindividual atthedoorifthedoorneedstoremainopenforanextendedperiodoftime.COOKNUCLEARPLANT-UNIT2B3/49-3AMENDMENT NO.

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