ML17328A753

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Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements Re Charging Pump - Shutdown & Pressure/Temp Limits for RCS
ML17328A753
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Site: Cook American Electric Power icon.png
Issue date: 10/29/1990
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INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
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ATTACHMENT 2TOAEP:NRC:08940 PROPOSEDREVISEDTECHNICAL SPECIFICATION PAGES90ii020047 90i029'DR ADOCK050003i5PPNU

.~4 REACTIVITY CONTROLSYSTEMSCHARGINGPUMP-SHUTDOWNLIMITINGCONDITION FOROPERATION 3.1.2.3a.Onechargingpumpintheboroninjection flowpathrequiredbySpecification 3.1.2.1shallbeOPERABLEandcapableofbeingpoweredfromanOPERABLEemergency bus.b.Onechargingflowpathassociated withsupportofUnit2shutdownfunctions shallbeavailable.

APPLICABILITY:

Specification 3.1.2.3.a.

-MODES5and6Specification 3.1.2.3.b.

-AtalltimeswhenUnit2isinMODES1,2,3,or4.ACTION'.WithnochargingpumpOPERABLE, suspendalloperations involving COREALTERATIONS orposi.tive reactivity changes.**

b.WithmorethanonechargingpumpOPERABLEorwithasafetyinjection pump(s)OPERABLEwhenthetemperature ofanyRCScoldlegislessthan0orequalto152F,unlessthereactorvesselheadisremoved,removetheadditional chargingpump(s)andthesafetyinjection pump(s)motorcircuitbreakersfromtheelectrical powercircuitwithinonehour.c.Theprovisions ofSpecification 3.0.3arenotapplicable.

Inadditiontotheabove,whenSpecification 3.1.2.3.b isapplicable andtherequiredflowpathisnotavailable, returntherequiredflowpathtoavailable statuswithin7days,orprovideequivalent shutdowncapability inUnit2andreturntherequiredflowpathtoavailable statuswithinthenext60days,orhaveUnit2inHOTSTANDBYwithinthenext12hoursandHOTSHUTDOWNwithinthefollowing 24hours.e.Therequirements ofSpecification

3.0. 4arenotapplicable

whenSpecification 3.1.2.3.b applies.SURVEILLANCE REUIREMENTS 4.1.2.3.1 Theaboverequiredchargingpumpshallbedemonstrated OPERABLEbyverifying, thatonrecirculation flow,thepumpdevelopsadischarge pressureofgreaterthanorequalto2390psigwhentestedpursuanttoSpecification 4.0.5atleastonceper31days.+Amaximumofonecentrifugal chargingpumpshallbeOPERABLEwheneverthe0temperature ofoneormoreoftheRCScoldlegsislessthanorequalto152F.~~Forpurposesofthisspecifi,cation, additionofwaterfromtheRWSTdoesnotconstitute apositivereactivity additionprovidedtheboronconcentration intheRWSTisgreaterthantheminimumrequiredbySpecification 3.1.2.7.b.2.

COOKNUCLEARPLANT-UNIT13/41-11AMENDMENT NO.

REACTIVITY CONTROLSYSTEMSCHARGINGPUMP-SHUTDOWNLIMITINGCONDITION FOROPERATION 4.1.2.3.2 Allchargingpumpsandsafetyinjection pumps,excluding theaboverequiredOPERABLEchargingpump,shallbedemonstrated inoperable byverifying thatthemotorcircuitbreakershavebeenremovedfrom'heir electrical powersupplycircuitsatleastonceper12hours,exceptwhen:a.Thereactorvesselheadisremoved,or0b.Thetemperature ofallRCScoldlegsisgreaterthan152F4.1.2.3.3 Charginglinecross-tie valvestoUnit2willbecycledfulltravelatleastonceper18months.Following cycling,thevalveswillbeverifiedtobeintheirclosedpositions.

COOKNUCLEARPLANT-UNIT13/41-llaAMENDMENT NO.

REACTORCOOLANTSYSTEMSHUTDOWNLIMITINGCONDITION FOROPERATION 3.4.1.3a.ThecoolantloopslistedbelowshallbeOPERABLEandinoperation asrequiredbyitemsbandc:1.ReactorCoolantLoop1anditsassociated steamgenerator andreactorcoolantpump,~2.ReactorCoolantLoop2anditsassociated steamgenerator andreactorcoolantpump,*3.ReactorCoolantLoop3anditsassociated steamgenerator andreactorcoolantpump,*4.ReactorCoolantLoop4anditsassociated steamgenerator andreactorcoolantpump,*5.ResidualHeatRemoval-East,~~6.ResidualHeatRemoval-West,*~b.AtleasttwooftheabovecoolantloopsshallbeOPERABLEandatleastoneloopinoperation ifthereactortripbreakersareintheopenposition, orthecontrolroddrivesystemisnotcapableofrodwithdrawal.~**

c.AtleastthreeoftheabovereactorcoolantloopsshallbeOPERABLEandinoperation whenthereactortripsystembreakersareintheclosedpositionandthecontrolroddrivesystemiscapableofrodwithdrawal.

APPLICABILITY:

MODES4and5+AreactorcoolantpumpshallnotbestartedwithoneormoreoftheRCScoldlegtemperatures lessthanorequalto152Funless1)thepressurizer

!0watervolumeislessthan62%ofspanor2)thesecondary water0temperature ofeachsteamgenerator islessthan50FaboveeachoftheRCScoldlegtemperatures.

Operability ofareactorcoolantloop(s)doesnotrequireanOPERABLEauxiliary feedwater system.**Thenormaloremergency powersourcemaybeinoperable inMODE5.>*>Allreactorcoolantpumpsandresidualheatremovalpumpsmaybede-energized forupto1hourprovided1)nooperations arepermitted thatwouldcausedilutionofthereactorcoolantsystemboronconcentration+~**,

and2)coreoutlettemperature ismaintained atleast010Fbelowsaturation temperature.

        • Forpurposesofthisspecification, additionofwaterfromtheRWSTdoesnotconstitute adilutionactivityprovidedtheboronconcentration intheRWSTisgreaterthanorequaltotheminimumrequiredbyspecification 3.1.2.8.b.2 (MODE4)or3.1.2.7.b.2 (MODE5).D.C.COOK-UNIT13/44-3AMENDMENT NO.

REACTORCOOLANTSYSTEM34.4.9PRESSURETEMPERATURE LIMITSREACTORCOOLANTSYSTEMLIMITINGCONDITION FOROPERATION 3.4.9.1TheReactorCoolantSystem(exceptthepressurizer) temperature andpressureshallbelimitedinaccordance withthelimitlinesshownonFigures3.4-2and3.4-3duringheatup,cooldown, criticality, andinservice leakandhydrostatic testingwith:a.Amaximumheatupof60Finanyonehourperiod,0b.Amaximumcooldownof100Finanyonehourperiod,and0c.Amaximumtemperature changeof<5Finanyonehourperiod,0duringhydrostatic testingoperations abovesystemdesignpressure.

APPLICABILITY:

Atalltimes'ACTION:Withanyoftheabovelimitsexceeded, restorethetemperature and/orpressuretowithinthelimitwithin30minutes;performananalysistodetermine theeffectsoftheout-of-limit condition onthefracturetoughness properties oftheReactorCoolantSystem;determine thattheReactorCoolantSystemremainsacceptable forcontinued operations orbeinatleastHOTSTANDBYwithinthenext6hoursandreducetheRCSTavgandpressuretolessthan200Fand500psig,respectively, withinthefollowing 30hours.*SeeSpecialTextException 3.10.3.COOKNUCLEARPLANT-UNIT13/44-25 onooIC:KM260024002200"REACTORCOOLANTSYSTEMHEATUPLIMITATIONS APPLICABLE FORFIRST32EFFECTIVE FULLPOWERYEARS(MARGINSOF60PSIGAND10FAREINCLUDED'ORPOSSIBLEINSTRUMENT ERROR.)MCOCI.IIICCDCIIIIICCCLCllX6IJJI-CoIIVCOI-XooOoIotljCC200018001600140012001000800600LEAKTESTLIMIT-UNACCEPTABLE OPERATION PRESSURE-TEMPERATURE LIMITFORHEATUPRATESUPTO600F/HR--------CRITICALITY LIMITACCEPTABLE OPERATION IllXoIll'zXo4002000L50100MATERIALPROPERTYBASISINTERMEDIATE PLATE,B4406-3Cu~.15Y,Ni~.49IINITIALRT400F.32EFPYRT1/4T~171F3/4T1360FL.I4004501502002503003500AVERAGEREACTORCOOLANTSYSTEMTEMPERATURE (F)FIGURE3.4-2REACTORCOOLANTSYSTEMPRESSURE-TEMPERATURE LIMITSVERSUS6dF/HRRATECRITICALITY LIMITANDHYDROSTATIC TESTLIMIT OoAooXIM260024002200REACTORCOOLANTSYSTEMCOOLDOWNLIHITATIONS APPLICABLE FORFIRST32EFFECTIVE FULLPOWERYEARS(MARGINS OF60PSIGAND10FAREINCLUDEDFORPOSSIBLEINSTRUMENT ERROR.)200018001600(g)1400I0-z1200o1000oI-oPRESSURE-TEMPERATURE LIMITSUNACCEPTABLE OPERATION ACCEPTABLE OPERATION 600400200COOLDOWNRATEDF/HR%860100HATERIALPROPERTYBASISINTERMEDIATE PLATE,B4406-3Cu.15X,Ni.49%INITIALRT40F32EFPYRT1/4T~171F3/4T~138DFITlKoPl'zI50100150200250300350AVERAGEREACTORCOOLANTSYSTEMTEHPERATURE (F)0FIGURE3.4-3400450KoREACTORCOOLANTSYSTEHPRESSURE-TEMPERATURE LIHITSVERSUSCOOLDOWHRATES REACTORCOOLANTSYSTEMOVERPRESSURE PROTECTION SYSTEMSLIMITINGCONDITION FOROPERATION 3.4.9.3Atleastoneofthefollowing overpressure protection systemsshallbeOPERABLE:

a.Twopoweroperatedreliefvalves(PORVs)withaliftsettingoflessthanor'qualto435psig,orb.Onepoweroperatedreliefvalve(PORV)withaliftsettingoflessthanorequalto435psigandtheRHRsafetyvalvewithaliftsettingoflessthanorequalto450psig,orc.Areactorcoolantsystemventofgreaterthanorequalto2squareinches.APPLICABILITY:

Whenthetemperature ofoneormoreoftheRCScoldlegsis0lessthanorequalto152F,exceptwhenthereactorvesselheadisremoved.ACTION'ith twoPORV'sinoperable orwithonePORVinoperable andtheRHRsafetyvalveinoperable, eitherrestoretheinoperable PORV(s)orRHRsafetyvalvetoOPERABLEstatuswithin7daysordepressurize andventtheRCSthroughanatleast2squareinchvent(s)withinthenext8hours;maintaintheRCSinaventedcondition untiltheinoperable PORVorRHRsafetyvalvehasbeenrestoredtoOPERABLEstatus.b.WithbothPORVsinoperable, depressurize andventtheRCSthroughanatleast2squareinchvent(s)within8hours;maintaintheRCSinaventedcondition untilbothPORVsoronePORVandtheRHRsafetyvalvehavebeenrestoredtoOPERABLEstatus.IntheeventeitherthePORVs,theRHRsafetyvalveortheRCSvent(s)areusedtomitigateaRCSpressuretransient, aSpecialReportshallbepreparedandsubmitted totheCommission pursuanttoSpecification 6.9.2within30days.Thereportshalldescribethecircumstances initiating thetransient, theeffectofthePORVsorvent(s)onthetransient andanycorrective actionnecessary topreventrecurrence.

d.Theprovisions ofSpecification 3.0.4arenotapplicable.

COOKNUCLEARPLANT-UNIT13/44-31AMENDMENT NO.

EMERGENCY CORECOOLINGSYSTEMSECCSSUBSYSTEMS

-Tav(350FLIMITINGCONDITION FOROPERATION 3.5.3Asaminimum,oneECCSsubsystem comprised ofthefollowing shallbeOPERABLE:

a.OneOPERABLEcentrifugal chargingpump,¹b.OneOPERABLEresidualheatremovalheatexchanger, c.OneOPERABLEresidualheatremovalpump,andd.AnOPERABLEflowpathcapableoftakingsuctionfromtherefueling waterstoragetankuponbeingmanuallyrealigned andtransferring suctiontothecontainment sumpduringtherecirculation phaseofoperation.

APPLICABILITY:

MODE4.ACTION:a~WithnoECCSsubsystem OPERABLEbecauseoftheinoperability ofeitherthecentrifugal chargingpumportheflowpathfromtherefueling waterstoragetank,restoreatleastoneECCSsubsystem toOPERABLEstatuswithin1hourorbeinCOLDSHUTDOWNwithinthenext20hours.b.WithnoECCSsubsystem OPERABLEbecauseoftheinoperability ofeithertheresidualheatremovalheatexchanger orresidualheatremovalpump,restoreatleastoneECCSsubsystem toOPERABLE0statusormaintaintheReactorCoolantSystemTavglessthan350Fbyuseofalternate heatremovalmethods.WithmorethanonechargingpumpOPERABLEorwithasafetyinjection pump(s)OPERABLEwhenthetemperature ofanyRCScoldlegislessthanorequalto152F,removetheadditional chargingpump(s)andthesafetyinjection pump(s)motorcircuitbreakersfromtheelectrical powercircuitwithin1hour.d.IntheeventtheECCSisactuatedandinjectswaterintotheReactorCoolantSystem,aSpecialReportshallbepreparedandsubmitted totheCommission pursuanttoSpecification 6.9.2within90daysdescribing thecircumstances oftheactuation andthetotalaccumulated actuation cyclestodate.¹Amaximumofonecentrifugal chargingpumpshallbeOPERABLEandbothsafetyinjection pumpsshallbeinoperable wheneverthetemperature ofoneormoreoftheRCScoldlegsislessthanorequalto152F.COOKNUCLEARPLANT-UNIT13/45-7AMENDMENT NO.

EMERGENCY CORECOOLINGSYSTEMSSURVEILLANCE REUIREMENTS 4.5'.1TheECCSsubsystem shallbedemonstrated OPERABLEpertheapplicable Surveillance Requirements of4.5.2.*4.5.3.2Allchargingpumpsandsafetyinjection pumps,excepttheaboverequiredOPERABLEchargingpump,shallbedemonstrated inoperable, byverifying thatthemotorcircuitbreakershavebeenremovedfromtheirelectrical powersupplycircuits, atleastonceper12hourswheneverthetemgerature ofoneormoreoftheRCScoldlegsislessthanorequalto152Fasdetermined atleastonceperhourwhenanyRCScoldlegtemperature isbetween152Fand200F.*Theprovisions ofSpecification 4.0.6areapplicable.

COOKNUCLEARPLANT-UNIT13/45-8AMENDMENT NO.

34.1REACTIVITY CONTROLSYSTEMSBASES34.1.1.4MODERATOR TEMPERATURE COEFFICIENT MTCContinued concentration associated withfuelburnup.Theconfirmation thatthemeasuredandappropriately compensated MTCvalueiswithintheallowable tolerance ofthepredicted valueprovidesadditional assurances thatthecoefficient willbemaintained withinitslimitsduringintervals betweenmeasurement.

34.1.1.5MINIMUMTEMPERATURE FORCRITICALITY Thisspecification ensuresthatthereactorwillnotbemadecritical0withtheReactorCoolantSystemaveragetemperature lessthan541F.Thislimitation isrequiredtoensure1)themoderator temperature coefficient iswithinitsanalyzedtemperature range,2)theprotective instrumentation iswithinitsnormaloperating range,and3)thepressurizer iscapableofbeinginanOPERABLEstatuswithasteambubble,and4)thereactorpressurevesselisaboveitsminimumRTtemperature.

Administrative procedures willbeestablished toensuret5eP-12blockedfunctions areunblocked beforetakingthereactorcritical.

34.1.2BORATIONSYSTEMSTheboroninjection systemensuresthatnegativereactivity controlisavailable duringeachmodeoffacilityoperation.

Thecomponents requiredtoperformthisfunctioninclude1)boratedwatersources,2)chargingpumps,3)separateflowpaths,4)boricacidtransferpumps,5)associated heattracingsystems,and6)anemergency powersupplyfromOPERABLEdieselgenerators.

WiththeRCSaveragetemperature above200F,aminimumoftwoseparate0andredundant boroninjection systemsareprovidedtoensuresinglefunctional capability intheeventanassumedfailurerendersoneofthesystemsinoperable.

Allowable out-of-service periodsensurethatminorcomponent repairorcorrective actionmaybecompleted withoutunduerisktooverallfacilitysafetyfrominjection systemfailuresduringtherepairperiod.Thelimitation foramaximumofonecentrifugal chargingpumptobeOPERABLEandtheSurveillance Requirement toverifyallchargingpumpsandsafetyinjection pumgs,excepttherequiredOPERABLEchargingpump,tobeinoperable below152F,unlessthereactorvesselheadisremoved,providesassurance thatamassadditionpressuretransient canberelievedbytheoperation ofasinglePORV.Theborationcapability ofeithersystemissufficient toprovidetherequiredSHUTDOWNMARGINfromalloperating conditions afterxenondecayandcooldownto200F.Themaximumexpectedborationcapability, usablevolume0requirement, is5641gallonsof20,000ppmboratedwaterfromtheboricacid.storagetanksor99,598gallonsof2400ppmboratedwaterfromtherefueling waterstoragetank.Theminimumcontained RWSTvolumeisbasedonECCSconsiderations.

SeeSectionB3/4.5.5.COOKNUCLEARPLANT-UNIT1B3/41-2AMENDMENT NO.

34.4REACTORCOOLANTSYSTEMBASES34.4.1REACTORCOOLANTLOOPSTheplantisdesignedtooperatewithallreactorcoolantloopsinoperation, andmaintainDNBRabove1.69duringallnormaloperations andanticipated transients.

Alossofflowintwoloopswillcauseareactortripifoperating aboveP-7(11percentofRATEDTHERMALPOWER)whilealossoflowinoneloopwillcauseareactortripifoperating aboveP-8(31percentofRATEDTHERMALPOWER).InMODE3,asinglereactorcoolantloopprovidessufficient heatremovalcapability forremovingdecayheat;however,singlefailureconsiderations requirethattwoloopsbeOPERABLE.

ThreeloopsarerequiredtobeOPERABLEandtooperateifthecontrolrodsarecapableofwithdrawal andthereactortripbreakersareclosed.Therequirement assuresadequateDNBRmarginintheeventofanuncontrolled rodwithdrawal inthismode.InMODES4and5,asinglereactorcoolantlooporRHRloopprovidessufficient heatremovalcapabi.lity forremovingdecayheat;butsinglefailureconsiderations requirethatatleasttwoloopsbeOPERABLE.

Thus,ifthereactorcoolantloopsarenotOPERABLE, thisspecification requirestwoRHRloopstobeOPERABLE.

Theoperation ofoneReactorCoolantPumporoneRHRpumpprovidesadequateflowtoensuremixing,preventstratification andproducegradualreactivity changesduringboronconcentration reductions intheReactorCoolantSystem.Thereactivity changerateassociated withboronreduction will,therefore, bewithinthecapability ofoperatorrecognition andcontrol.Therestrictions onstartingaReactorCoolantPumpbelowP-7withoneormoreRCScoldlegslessthanorequalto152FareprovidedtopreventRCSpressuretransients, causedbyenergyadditions fromthesecondary system,whichcouldexceedthelimitsofAppendixGto10CFRPart50.TheRCSwillbeprotected againstoverpressure transients andwillnotexceedthelimitsofAppendixGbyeither(1)restricting thewatervolumeinthepressurizer andtherebyproviding avolumefortheprimarycoolanttoexpandintoor(2)byrestricting startingoftheRCP'stowhenthesecondary watertemperature ofeachsteamgenerator islessthan50FaboveeachoftheRCScoldleg0temperatures.

COOKNUCLEARPLANT-UNIT1B3/44-1AMENDMENT NO.

REACTORCOOLANTSYSTEMBASES34.4.9PRESSURETEMPERATURE LIMITSAllcomponents intheReactorCoolantSystemaredesignedtowithstand theeffectsofcyclicloadsduetosystemtemperature andpressurechanges.Thesecyclicloadsareintroduced bynormalloadtransients, reactortrips,andstartupandshutdownoperations.

Thevariouscategories ofloadcyclesusedfordesignpurposesareprovidedinSection4.1.4oftheFSAR.Duringstartupandshutdown, theratesoftemperature andpressurechangesarelimitedsothatthemaximumspecified heatupandcooldownratesareconsistent withthedesignassumptions andsatisfythestresslimitsforcyclicoperation.

AnIDorODone-quarter thickness surfaceflawispostulated atthelocationinthevesselwhichisfoundtobethelimitingcase.Thereareseveralfactorswhichinfluence thepostulated location.

Thethermalinducedbendingstressduringheatupiscompressive ontheinnersurfacewhiletensileontheoutersurfaceofthevesselwall.Duringcooldownthebendingstressprofileisreversed.

Inaddition, thematerialtoughness isdependent uponirradiation andtemperature andtherefore thefluenceprofilethroughthereactorvesselwall,therateofheatupandalsotherateofcooldowninfluence thepostulated flawlocation.

Theheatuplimitcurve,Figure3.4-2,isacomposite curvewhichwaspreparedbydetermining themostconservative case,witheithertheinside0oroutsidewallcontrolling, foranyheatuprateupto60Fperhour.ThecooldownlimitcurvesofFigure3.4-3arecomposite curveswhichwerepreparedbaseduponthesametypeanalysiswiththeexception thatthecontrolling locationisalwaystheinsidewallwherethecooldownthermalgradients tendtoproducetensilestresseswhile,producing compressive stressesattheoutsidewall.Theheatupandcooldowncurveswerepreparedbaseduponthemostlimitingvalueofthepredicted adjustedreference temperature attheendof32EFPY.Reactoroperation andresultant fastneutron(E)1Mev)irradiation willcauseanincreaseintheRTN.Therefore, anadjustedreference temperature, baseduponthefluence,andPhecopperandnickelcontentofthematerialmustbepredicted.

TheheatupandcooldownlimitcurvesofFigures3.4-2and3.4-3includetheadjustedRTattheendof32EFPY,aswellasadjustments forpossibleerrorsinthepressureandtemperature sensinginstruments.

COOKNUCLEARPLANT-UNIT1B3/44-6AMENDMENT NO.

REACTORCOOLANTSYSTEMBASESThe32EFPYheatupandcooldowncurvesweredeveloped basedonthefollowing:

1.Theintermediate shellplate,B4406-3,beingthelimitingmaterial'ithacopperandnickelcontentof.15%and.49%respectively.

2.Thefluencevaluescontained inTable6-14ofWestinghouse's WCAP-12483 report,"Analysis ofCapsuleUFromtheAmericanElectricPowerCompanyD.C.CookUnit1ReactorVesselRadiation Surveillance Program,"

datedJanuary1990.3.Figure1,NRCRegulatory Guide1.99,Revision2TheshiftinRTNofthereactorvesselmaterialhasbeenestablished byremovingandevaluating thematerialsurveillance capsulesinstalled neartheinsidewallofthereactorvesselinaccordance withtheremovalscheduleinTable4.4-5.Perthisschedule, CapsuleUisthelastcapsuletoberemoveduntilCapsuleSistoberemovedafter32EFPY(EOL).CapsuleV,W,andZwillremaininthereactorvessel,andwillberemovedtoaddressindustryreactorembrittlement

concerns, ifrequired.

Thepressure-temperature limitlinesshownonFigure3.4-2forreactorcriticality andforinservice leakandhydrostatic testinghavebeenprovidedtoassurecompliance withtheminimumtemperature requirements ofAppendixGto10CFR50.Thenumberofreactorvesselirradiation surveillance specimens andthefrequencies forremovingandtestingthesespecimens areprovidedinTable4.4-5toassurecompliance withtherequirements ofAppendixHto10CFRPart50.Thelimitations imposedonpressurizer heatupandcooldownandspraywatertemperature differential areprovidedtoassurethatthepressurizer isoperatedwithinthedesigncriteriaassumedforthefatigueanalysisperformed inaccordance withtheASMECoderequirements.

TheOPERABILITY oftwoPORVs,onePORVandtheRHRsafetyvalve,oranRCSventopeningofgreaterthanorequalto2squareinchesensuresthattheRCSwillbeprotected frompressuretransients whichcouldexceedthelimitsofAppendixGto10CFRPart50whenoneormoreoftheRCScoldlegsarelessthanorequalto152F.EitherPORVorRHRsafetyvalvehasadequate0relieving capability toprotecttheRCSfromoverpressurization whenthetransient islimitedtoeither(1)thestartofanidleRCPwiththesecondary 0watertemperature ofthesteamgenerator lessthanorequalto50FabovetheRCScoldlegtemperatures or(2)thestartofachargingpumpanditsinjection intoawatersolidRCS.COOKNUCLEARPLANT-UNIT1B3/44-7AMENDMENT NO.

EMERGENCY CORECOOLINGSYSTEMBASESWiththeRCStemperature below350F,oneOPERABLEECCSsubsystem isacceptable withoutsinglefailureconsideration onthebasis6fthestablereactivity condition ofthereactorandthelimitedcorecoolingrequirements.

Thelimitation foramaximumofonecentri.fugal chargingpumptobeOPERABLEandtheSurveillance Requirement toverifyallchargingpumpsandsafetyinjection pumps,excepttherequiredOPERABLEchargingpump,tobeinoperable below152Fprovidesassurance thatamassadditionpressuretransient canberelievedbytheoperation ofasinglePORV.TheSurveillance Requirements providedtoensureOPERABILITY ofeachcomponent ensuresthatataminimum,theassumptions usedinthesafetyanalysesaremetandthatsubsystem OPERABILITY ismaintained.

Surveillance requirements forthrottlevalvepositionstopsandflowbalancetestingprovideassurance thatproperECCSflowswillbemaintained intheeventofaLOCA.Maintenance ofproperflowresistance andpressuredropinthepipingsystemtoeachinjection pointisnecessary to:(1)preventtotalpumpflowfromexceeding runoutconditions whenthesystemisinitsminimumresistance configuration, (2)providetheproperflowsplitbetweeninjection pointsinaccordance withtheassumptions usedintheECCS-LOCA

analyses, and(3)provideanacceptable leveloftotalECCSflowtoallinjection pointsequaltoorabovethatassumedintheECCS-LOCA analyses.

34.5.4BORONINJECTION SYSTEMTheOPERABILITY oftheboroninjection systemaspartoftheECCSensuresthatsufficient negativereactivity isinjectedintothecoretocounteract anypositiveincreaseinreactivity causedbyRCSsystemcooldown.

RCScooldowncanbecausedbyinadvertent depressurization, aloss-of-coolant accidentorasteamlinerupture.Thelimitsoninjection tankminimumcontained volumeandboronconcentration ensurethattheassumptions usedinthesteamlinebreakanalysisaremet.~TheOPERABILITY oftheredundant heattracingchannelsassociated withtheboroninjection systemensurethatthesolubility oftheboronsolutionwillbemaintained abovethesolubility limitof135Fat21000ppmboron.COOKNUCLEARPLANT-UNIT1B3/45-2AMENDMENT NO.

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