ML17334A963

Proposed Tech Spec Changes Re Containment Level Monitor,In Response to Generic Ltr 83-37

ML17334A963
Person / Time
Site:	Cook
Issue date:	05/19/1986
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17334A962	List: ML17334A961 ML17334A963
References
GL-83-37, NUDOCS 8605230211
Download: ML17334A963 (33)

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REACTORCOOLANT,SYSTEM3/4.4.6REACTORCOOLANTSYSTEMLEAKAGELEAKAGEDETECTION SYSTEMSLIMITINGCONDITION FOROPERATION 3.4.6.1Thefollowing ReactorCoolantSystemleakagedetection systemsshallbeOPERABLE:

'a~Oneofthecontainment atmosphere particulate radioactivity monitoring channels(ERS-1301 orERS-1401),

b.Thecontainment, sumpflowmonitoring system,andc~Eitherthecontainment humiditymonitoro"oneofthecontainment atmosphere gaseousradioactivity monitoring channels(ERS-1305 orERS-1405)

.APPLICABILITY:

MODES1,2,3and4.ACTION:Withonlytwooftheaboverequiredleakagedetection systemsOPERABLE, operation maycontinueforupto30daysprovidedgrabsamplesofthecontainment atmosphere areobtainedandanalyzedatleastonceper24hourswhentherecuiredgaseousand/crparticulate radioactivity monitoring channelsareinoperable; otherwise, beinatleastHOTSTANDBYwithinthene'xt6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.SURVEILLANCE REUIREMENTS 4.4.6.1Theleakagedetection systemsshallbedemonstrated OPERABLEby:'a~Containment atmosphere particulate andgaseous(ifbeingused)monitoring system-performance ofCHANNELCHECK,CHANNELCALIBRATION andCHANNELFUNCTIONAL TESTatthefrequencies specified inTable4.3-3,b.Containment sumpflowmonitoring system-performance ofCHANNELCALIBRATION atleastonceper18months,c~Containment humiditymonitor(ifbeingused)-performance ofCHANNELCALIBRATION atleastonceper18months.D.C.COOK-UNIT13/44-14~Amendment No.

ICl1 REACTORCOOLANTSYSTEMThispageintenzicnally leftblank.D.C.'OOK-UNIT13/44-15Amendment No.

ADMINISTRATIVE CONTROLSSPECIALREPORTS6.9.2Specialreportsshallbesubmitted totheRegionalAdministrator withinthetimeperiodspecified foreachreport.Thesereportsshallbesubmitted coveringtheactivities identified belowpursuanttotherequirements oftheapplicable reference Specifications:

a~b.c~Inservice Inspection ProgramReview,Specification 4.4.10.ECCSActuation, Specifications 3.5.2and3.5.3.Inoperable SeismicMonitoring Instrumentation, Specification 3.3.3.3.d.Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.e.Seismiceventanalysis, Specification 4.3.3.3.2.

f.SealedSourceleakageinexcessoflimits,Specification 4.7.7.1.3.

g.FireDetection Instrumentation, Specification 3.3.3.7.h.FireSuppression Systems,Specifications 3.7.9.1,3.7.9.2,3.7.9.3and3.7.9.4.i.Containment SumpLevelinstrumentation, Table3.3-11.D.C.COOK-UNIT16-19Amendment No.

INSTRUMENTATION BASES3/4.3.3.7 FIREDETECTION INSTRUMENTATION OPERABILITY ofthef'redetection instrumentation ensuresthatadequatewarningcapability isavailable forthepromptdetection offires.Thiscapability isrequiredinordertodetectandlocatefiresintheirearlystages.Promptdetection offireswillreducethepotential fordamagetosafetyrelatedequipment andisanintegralelementintheoverallfacilityfireprotection program.Intheeventthataportionofthefiredetection instrumentation isinoperable, theestablishment o'ffrequentfirepatrolsintheaffectedareasisrequiredtoprovidedetection capability untiltheinoperable instrumentation isrestoredtoOPERABILITY.

Useofcontainment temperature monitoring isallowedonceperhourifccntainment firedetection isinoperable.

3/4.3.3.8POST-ACCiDENT INSTRUMENTATION TheOPERABILITY ofthepost-accident instrumentation ensuresthatsufficient information isavailable onselectedplantparameters tomonitorandassessthesevariables duringandfollowing anaccident.

Thecontainment waterlevelCHANNELCHECKisavisualinspection ofparallelchannelswhichshouldindicatewithinacceptable instrument driftthatthewaterlevelisbelowtherangeoftheccntainment waterlevelinstrumentation.

Acceptable instrument driftforccntainment waterlevelinstrumentation ispresently considered 25%offullscale.Thecontainment sumplevelchannelsshouldindicatethesamelevelonbothchannelswithinacceptable instrument drift,whichispresently considered a25%offullscaledifference betweenthetwoparallelchannels.

Ifthechannelsdonotindicatethesamelevel,thecontainment sumppumpactuation andshut-offcanbeusedtoindicateifeitherchanneliscorrect.Thedriftforbothinstrumentation systemsisattributed toairaccumulation inthecapillaries.

Providedthatthedriftislessthan25%,itshouldnotpreventtheinstrument frcmtrackingchangesinlevel.Equipment changesmaychangetheacceptable drift.Suchachangewillnotconstitute violation ofthisT/S,providedappropriate evidenc'e existstojustifythechange.D.C.COOK-UNIT1B3/43-4Amendment No.

POS-CCIDENTISTRUMENTATION LIMITINGCONDITION FOROPERATION 3.3.3.8Thepost-accident monitoring instrumentation channelsshowninTable3.3-11shallbeOPERABLE.

APPLICABILITY:

MODES1,2,and3.ACTION:WiththenumberofOPERABLEpost-accident monitoring channelslessthanrequiredbyTable3.3-11,eitherrestoretheinoperable channeltoOPERABLEstatuswithin30days,orbeinHOTSHUTDOWNwithinthenext12hoursexceptwherenotedinTable3.3-11.b.Theprovisions ofSpecifications 3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.3.3.8Eachpost-accident monitoring instrumentation channelshallbedemonstrated OPERABLEbyperformance oftheCHANNELCHECKandCHANNELCALIBRATION operations atthefrequencies showninTable4.3-7.D.C.COOK-UNIT13/43-54Amendment No.

TABLE3.3-llPOST-ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT HINIHUHCHANNELSOPERABLE1.Containment Pressure2.3.4.ReactorCoolantOutletTemperature

-T(WideRange)HOTReactorCoolantInletTemperature

-T(WideRange)COLDReactorCoolantPressure-WideRange5.Pressurizer WaterLevel6.SteamLinePressure7.SteamGenerator WaterIevel-Na'rrowRange8.Refueling WaterStorageTankWaterLevel9.BoricAcidTankSolutionLevel10.AuxiliarFeedwater FlowRateYll.ReactorCoolantSystemSubcooling HarginMonitor12.PORVPositionIndicator

-LimitSwitches***

13.PORVBlockValvePositionIndicator

-LimitSwitches14.SafetyValvePositionIndicator

-AcousticMonitor15.Containment SumpLevel16.Containment WaterLevel2/SteamGenerator 1/SteamGenerator 1/SteamGenerator*

1**1/Valve1/Valve1/Valve1¹SteamGenerator WaterLevelChannelscanbeusedasasubstitute forthecorresponding auxiliary feedwater flowratechannelinstrument.

PRODAC250subcooling marginreadoutcanbeusedasasubstitute forthesubcooling monitorinstrument.

• • • Acousticmonitoring ofPORVposition(1channelperthreeval'ves-headereddischarge) canbeusedasasubstitute forthePORVPositionIndicator

-LimitSwitchesinstruments.

¹WithlessthantheminimumnumberofchannelsOpERABLErestorethesystemtoOPERABLEstatuswithin30daysorprepareandsubmitaSpecialReporttotheCommission pursuanttoSpecification 6.9.2withinthenext14daysoutlining available backupequipment, thecauseoftheinoperability andtheplansandscheduleforrestoring

..thesystemtoOPERABLEstatus.

TABLE4.3-7POST-ACCIDENT MONITORING INSTRUHENTATION SURVEILLANCE REUIREHENTS INSTRUMENT CHANNELCHECKCHANNELCALIBRATION 1.Containment Pressure2.ReactorCoolantOutletTemperature

-T(WideRange)HOT3.,ReactorCoolantInletTemperature

-T(WideRange)COLD4.ReactorCoolantPressure-WideRange5.Pressurizer WaterLevel6.SteamLinePressure7.SteamGenerator WaterLevel-NarrowRange8.RWSTWaterLevel9.BoricAcidTankSolutionLevel10.Auxiliary Feedwater FlowRate11.ReactorCoolantSystemSubcooling MarginMonitor12.PORVPositionIndicator

-LimitSwitches13.PORVBlockValvePositionIndicator

-LimitSwitches14.SafetyValvePositionIndicator

-AcousticMonitor15.Containment SumpLevel16.Containment WaterLevel INSE0POST-CCIDENTINSTRUMENTATION LIMITIGCODITIONFOROPERATON3.3.3,6Thepost-accident monitoring instrumentation channelsshowninTable3.3-10shallbeOPERABLE.

APPLICABILITY:

MODES1,2,and3.~ACTON:WiththenumberofOPERABLEpost-accident monitoring channelslessthanrequiredbyTable3.3-10,eitherrestoretheinoperable channeltoOPERABLEstatuswithin30days,orbeinHOTSHUTDOWNwithinthenext12hoursexceptwherenotedinTable3.3-10'.Theprovisions ofSpecifications 3.0.4arenotapplicable.

SURVEILLANCE REUIREMETS4.3.3.6Eachpost-accident monitoring instrumentation channelshallbedemonstrated OPERABLEbyperformance oftheCHANNELCHECKandCHANNELCALIBRATION operations atthefrequencies showninTable4.3-10.D.C.COOK-UNIT23t43-45Amendment No.

TABLE3.3-10POST-ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUMCHANNELSOPERABLE1.Containment Pressure2.3.45.ReactorCoolantOutletTemperature

-T(WideRange)ReactorCoolantInletTemperature

-T(WideRange)ReactorCoolantPressure-WideRangePressurizer WaterLevel'.SteamLinePressure7.SteamGenerator WaterLevel-NarrowRange8.Refueling WaterStorageTankWaterLevel9.BoricAcidTankSolutionLevel10.Auxiliary Feedwater FlowRate11.ReactorCoolantSystemSubcooling MarginMonitor12.PORVPositionIndicator

-LimitSwitches"-**

13.PORVBlockValvePositionIndicator

-LimitSwitches14.SafetyValvePositionIndicator

-AcousticMonitor15.Containment SumpLevel16.Containment WaterLevel2/SteamGenerator 1/SteamGenerator 1/SteamGenerator*

1/Valve1/Valve1/Valve*SteamGenerator WaterLevelChannelscanbeusedasasubstitute forthecorresponding auxiliary feedwater flowratechannelinstrument.

.**pRODAC250subcooling marginreadoutcanbeusedasasubstitute forthesubcooling monitorinstrument.

• • • Acousticmonitoring ofPORVposition(1channelperthreevalves-headereddischarge) canbeusedasasubstitute forthePORVPositionIndicator

-LimitSwitchesinstruments.

WithlessthantheminimumnumberofchannelsOPERABLErestorethesystemtoOPERABLEstatuswithin30daysorprepareandsubmitaSpecialReporttotheCommission pursuanttoSpecification 6.9.2withinthenext14daysoutlining available backupequipment, thecauseoftheinoperability andtheplansandscheduleforrestoring thesystemtoOPERABLEstatus.

TABLE4.3-10POST-ACCIDENT HONITORING INSTRUMENTATION SURVEILLANCE REUIREHENTS INSTRUMENT CHANNELCHECKCHANNELCALIBRATION 1.Containment Pressure2.3.5."ReactorCoolantOutletTemperature

-T(WideRange)HOTReactorCoolantInletTemperature

-T(WideRange)COLDReactorCoolantPressure-WideRangePressurizer WaterLevelR6.SteamLinePressure7.SteamGenerator WaterLevel-NarrowRange0.RWSTWaterLevel9.BoricAcidTankSolutionLevel10.Auxzlzary Feedwater FlowRatell.ReactorCoolantSystemSubcooling MarginMonitor12.PORVPositionIndicator

-LimitSwitches13.PORVBlockValve-Position Indicator

-LimitSwitches" 14.SafetyValvePositionIndicator

-AcousticMonitor15.Containment SumpLevel16.Containment WaterLevel*Theprovisions ofSpecification 4.0.6areapplicable.

REACTORCOOLANTSYSTEM3/4.4.6REACTORCOOLANTSYSTEMLEAKAGELEAKAGEDETECTION SYSTEMSLIMITINGCONDITION FOROPERATION 3.4.6.1"Thefollowing FeactorCoolantSystemleakagedetection systemsshallbeOPERABLE:

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

b.Thecontainment sumpflowmonitoring system,andc.Eitherthecontainment humiditymonitororoneofthecontainment atmosphere gaseousradioactivity monitoring channels~(ERS-2305 orERS-2405).

APPLICABILITY:

MODES1,2,3and4.ACTXON:Withonlytwooftheabcverecuiredleakagedetection systemsOPERABLE, operation maycontinueforuptc30daysprovidedcrabsamplesofthecontainment atmosphere aeobtainedandanalyzedatleastonceper24hourswhentherequiredgasecusand/crparticulate radioactivity monitoring channelsareinoperable; otherwise, beinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.SURVEILLANCE REUIREMENTS 4.4.6.1Theleakagedetection systemsshallbedemonstrated OPERABLEby:a~Containment atmosphere particulate andgaseous(ifbeingused)monitoring system-performance ofCHANNELCHECK,CHANNELCALIBRATION andCHANNELFUNCTIONAL TESTatthefrequencies specified inTable4.3-3,b.Containment sumpflowmonitoring system-performance ofCHANNELCALIBRATION atleastonceper18months,*C~Containment humiditymonitor(ifbeingused)-performance ofCHANNELCALIBRATION atleastonceper18months.*Theprovisions ofSpecification 4.0.6areapplicable.

D.C.COOK-UNIT23/44-14Amendment No.

ADMINISTRATIVE CONTROLSSPECIALREPORTS6.9.2Specialreportsshallbesubmitted totheRegionalAdministrator withinthetimeperiodspecified foreachreport.Thesereportsshallbesubmitted coveringtheactivities identified belowpursuanttotherequirements oftheapplicable reference specification:

a0ECCSActuation, Specifications 3.5.2and3,5.3.b.Inoperable SeismicMonitoring Instrumentation, UnitNo.1,Specification 3.3.3.3.c~Inoperable Meteorological Monitoring Instrumentation, UnitNo.1,Specification 3.3.3.4.d.FireDetection Instrumentation, Specification 3.3.3.8.e.FireSuppression Systems,Specifications, 3.7.9.1,3.7.9.2,3.7.9.3and3.7.9.4.SeismicEventAnalysis, Specification 4.3.3.3.2.

g.SealedSourceleakageinexcessoflimits,Specification 4.7.8.1.3.

h.Containment SumpLevelinstrumentation, Table3.3-10.D.C.COOK-UNIT26-19Amendment No.

13/4~3INSTRUMENTATZ BASES3/4.3>3~2MOVABLEZNCOREDETECTORS TheOPERABILITY ofthemovableincoredetectors withthespecified minimumcomplement ofequipment ensuresthatthemeasurements obtainedforuseofthissystemaccurately represent thespatialneutronfluxdistribution ofthereactorcore.TheOPERABILITY ofthissystemisdemonstrated byirradiating eachdetectorusedandnormalizing itsrespective output.3/4.3.3.3 SEISMICINSTRUMENTATION TheOPERABILITY oftheseismicinstrumentation ensuresthatsufficient capability isavailable topromptlydetermine themagnitude ofaseismicevent,andevaluatetheresponseofthosefeaturesimportant tosafety.Thiscapability isrequiredtopermitcomparison ofthemeasuredresponsetothatusedinthedesignbasisforthefacility.

3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION TheOPERABILITY ofthemeteorological instrumentation ensuresthatsufficient meteorological dataisavailable forestimating potential radiation dosestothepublicasaresultofroutineoraccidental releaseofradioactive materials totheatmosphere.

Thiscapability isrequiredtoevaluatetheneedforinitiating protective measurestoprotectthehealthandsafetyofthepublic.3/4.3.3.5 REMOTESHUTDOWNINSTRUMENTATZON TheOPERABILITY oftheremote'hutdown instrumentation ensuresthatsufficient capability isavailable topermitshutdownandmaintenance ofHOTSTANDBYofthefacilityfromlocations outsideofthecontrolroom.Thiscapability isrequiredintheeventcontrolroomhabitability islostandisconsistent withGeneralDesignCriteria19of10CFR50.3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION TheOPERABILITY ofthepost-accident instrumentation ensuresthatsufficient information isavailable onselectedplantparameters tomonitorandassessthesevariables duringandfollowing anaccident.

Thecontainment waterlevelCHANNELCHECKisavisualinspection ofparallelchannelswhichshouldindicatewithinacceptable instrument driftthatthewaterlevelisbelowtherangeofthecontainment waterlevelinstrumentation.

Acceptable instrument driftforcontainment waterlevelinstrumentation ispresently considered 25%offullscale.Thecontainment sumplevelchannelsshouldindicatethesamelevelonbothchannelswithinacceptable instrument drift,whichispresently considered a25%offullscaledifference betweenthetwoparallelchannels.

Ifthechannelsdonotindicatethesamelevel,thecontainment sumppumpactuation andshut-offcanbeusedtoindicateifeitherchanneliscorrect.D.C.COOK-UNIT2B3/43-2Amendment No.

3/4.3INSTRUMENTATION BASESThedriftforbothinstrumentation systemsisattributed toairaccumulation inthecapillaries.

Providedthatthedriftislessthan25%,itshouldnotpreventtheinstumentromtrackingchangesinlevel.Equipment changesmaychangetheacceptable drift.Suchachangewillnotconstitute aviolation ofthisT/S,prov'dedappropriate evidenceexiststojustifythechange.3/4.3.3.7AXIALPOWERDISTRIBUTION MONITORING SYSTEM(APDMS)OPERABILITY oftheAPDMSensuesthatsufficient capability isavailable forthemeasurement oftheneutronfluxspatialdistribution withinthereactorcore.Thiscapability isrequiredto1)monitorthecorefluxpatternsthatarerepresentative ofthepeakcorepowerdensityand2)limitthecoreaverageaxialpowerprofilesuchthat~thetotalpowerpeakingfactorFismaintained withinacceptable limits.3/4.3.3.8 FIREDETECTION ZNSTRUMENTATZON OPERABILITY ofthefiredetection instrumentation ensuresthatadequatewarningcapability isavailable forthepromptdetection offires.Thiscapability isrequiredinordertodetectandlocatefiresintheirearlystages.Promptdetection off'reswillreducethepotential fordamagetosafety-related equipment andisanintegralelementintheoverallfacilityfireprotection program.Zntheeventthataportionofthefiredetection instrumentation isinoperable, theestablishment offrequentfirepatrolsintheaffectedareasisrequiredtoprovidedetection capability untiltheinoperable instrumentation isrestoredtcOPERABILITY.

Useofcontainment temperature monitoring isallowedonceperhourifcontainment firedetection isinoperable.

3/4.3.3.9PADIOACTIVE LZUZDEFFLUENTINSTRUMENTATION Theradioactive liquideffluentinstrumentation isprovidedtomonitorandcontrol,asapplicable, thereleasesofradioactive materials inliquideffluents duringactualorpotential releases.

Thealarm/trip setpoints fortheseinstruments shallbecalculated inaccordance withNRCapprovedmethodsintheODCMtoensurethatthealarm/trip willoccurpriortoexceeding thelimitsof10CFRPart20.TheOPERABILITY anduseofthisinstrumentation isconsistent withtherequirements ofGeneralDesignCriteriaspecified inSection11.3oftheFinalSafetyAnalysisReportfortheDonaldC.CookNuclearPlant.3/4.3.3.10 RADIOACTIVE GASEOUSEFFLUENTINSTRUMENTATION Theradioactive gaseouseffluentinstrumentation isprovidedtomonitorandcontrol,asapplicable, thereleasesofradioactive materials ingaseouseffluents duringactualorpotential releases.

Thealarm/trip setpoints fortheseinstruments shallbecalculated inaccordance withNRCapprovedmethodsD.C.COOK-UNIT2B3/43-3Amendment No.

1I~~~~3/4.3INSTRUMENTATION BASESintheODCMtoensurethatthealarm/trip willoccurpriortoexceeding thelimitsof10CFRPart20.Thisinstrumentation alsoincludesprovisions formonitoring theconcentrations ofpotentially explosive gasmixturesinthewastegasholdupsystem.TheOPERABILITY anduseofthisinstrumentation isconsistent withtherequirements ofGeneralDesignCriteriaspecified in'ection11.3ofthe'Final SafetyAnalysisReportfortheDonaldC.CookNuclearPlant.3/4.3.4TURBINEOVERSPEED PROTECTION Thisspecification isprovidedtoensurethattheturbineoverspeed protection instrumentation andtheturbinespeedcontrolvalvesareOPERABLEandwillprotecttheturbineromexcessive overspeed.

Protection fromturbineexcessive overspeed isrequiredsinceexcessive overspeed oftheturbinecouldgeneratepotentially damagingmissileswhichcouldimpactanddamagesafetyrelatedcomponents, equipment orstructures.

D.C.COOK-Unit2B3/43-4Amendment No.

u~~(3~QorloinystlllfDIANA

&NICH~GAIV ElECTBICCOFORTWAYNE,INDIANAAMOUNTcHEcKNo.083~0273DATE03248bSl50.004~lnfullseNIement ofstatement accompenytng thischeUSNUCLEARREGULATORY COMMISSIONTotheWASHINGTON DC20555Orderof25b43024DISBURSEMENT ACCOUNTLINCOLNNATIONALBANKANDTRUSTCOMPANY,FORTWAYNE,INDIANAII'029LI3II.07t900275I:I3S75205ll'EMITTANCE ADVICE-DETACHBEFOREDEPOSITING INDIANALMICHIGANELECTRICCO.P.O.BOX60FORTWAYNE,INDIANA46801cHEGKNo.0630273OURREFERENCE DATE036030'I602-2b-86DATE03248bVENDORSREFERENCE

,AEPNRCor5'I2pfAMOUNTGROSS15000$15000DEDUCTTRY32REV.I86EXPLANATION CD-CASHDISCOUNTRT-RETAINEDPRPRIORPAYMENTOFDEDUCTIONS TR-TRANSPORTATION TXTAXWITHHELDAJADJUSTMENT Attachment 3toAEP:NRC:0856T Regulatory Guide1.97,Rev.3,Pertinent Sections

~O'">>U.S.NUCLIRREGULATORY COMMI88lot

!RELATRY0FRCEOFNUCLEARREGULATORY RESEARCHResea~aa'D-REGULATORY GUIDE'l.97INSTRUMENTATION FORLIGHT-WATEROOLED NUCLEARPOWERPLANTSTOASSESSPLANTANDENVIRONSCONDITIONS DURINGANDFOLLOWING ANACCIDENTA.INTROOUCTION B.OISCUSSION Criterion 13,"Instrumentation andControl,"

ofAppen-dixA,"GeneralDesignCriteriaforNuclearPowerPlants,"to10CFRPart50,"Domestic Licensing ofProduction andUtilization Facilities,"

includesarequirement thatinstru-mentation beprovidedtomonitorvariables andsystemsovertheiranticipated rangesforaccidentconditions asappropriate toensureadequatesafety.Criterion 19,"ControlRoofn,"ofAppendixAto10CFRPart50includesarequirement thatacontrolroombepro-,videdfromwhichactionscanbetakentomaintainthenuclearpowerunitinasafecondition underaccidentconditions, including losswfwoolant accidents, andthatequipment, including thenecessary instrumentation, atappropri'ate locations outsidethecontrolroombe.providedwithadesigncapability forprompthotshutdownofthereactor.Criterion 64,"Monitoring Radioactivity Releases,"

ofAppendixAto10CFRPart50includesarequirement thatmeansbeprovidedformonitoring thereactorcontainment atmosphere, spacescontaining components forrecirculation oflo~fwoolant accidentfluid,effluentdischarge paths,andtheplantenvironsforradioactivity thatmaybereleasedfrompostulated accidents.

Indications ofplantvariables arerequiredbythecontrolroomoperating personnel duringaccidentsituations to(1)provideinformation requiredtopermittheoperatortotakepreplanned manualactionstoaccomplish safeplantshut-down;(2)determine whetherthereactortrip,engineered-safety-feature systems,andmanuallyinitiated safetysystemsandothersystemsimportant tosafetyareperforming theirintendedfunctions (i.ereactivity control,core.cooling,maintaining reactorcoolantsystemintegrity, andmaintaining containment integrity);

and(3)provideinforma-tiontotheoperators thatwillenablethemtodetermine thepotential forcausingagrossbreachofthebarrierstoradioactivity release(i.e.,fuelchdding,reactorcoohntpressureboundary, andcontainment) andtodetermine ifagrossbreachofabarrierhasoccurred.

Inadditiontotheabove,indications ofplantvariables thatprovideinforma-tiononoperation ofplantsafetysystemsandothersystemsimportant tosafetyarerequiredbythecontrolroomoperating personnel duringanaccidentto(I)furnishdataregarding theoperation ofplantsystemsinorderthattheoperatorcanmakeappropriate decisions astotheiruseand(2)provideinformation regarding thereleaseofradioactive materials toallowforearlyindication oftheneedtoinitiateactionnecessary toprotectthepublicandforanestimateofthemagnitude ofanyimpending threat.Thisguidedescribes amethodacceptable totheNRCstaffforcomplying withtheCommission's regulations toprovideinstrumentation tomonitorplantvariables andsystemsduringandfollowing anaccidentinalight-water-coolednuclearpowerplant.'IheAdvisoryCommittee onReactorSafeguards hasbeenconsulted concerning thisguideandhasconcurred intheregulatory position.

Anyguidanceinthisdocumentrelatedtoinformation collection activities hasbeenclearedunderOMBClearance No.31504011.

Atthestartofanaccident, itmaybedifficult fortheoperatortodetermine immediately whataccidenthasoccurredorisoccurring andtherefore todetermine theappropriate

response, Forthisreason,reactortripandcertainothersafetyactions(e.g.,emergency corecoolingactuation, containment isolation, ordepressurization) havebeendesignedtobeperformed automatically duringtheinitialstagesofanaccident.

Instrumentation isalsoprovidedtoindicateinformation aboutphntvariables requiredtoenabletheoperation ofmanuallyinitiated safetysystemsandotherappropriate operatoractionsinvolving systemsimportant tosafety.USNRCREGULATORY GUIDESRagulatary GuidesaceIssuedtodescribeandmakeavailable tothepubliccnethodsacceptable totheNRcstaffofImplementing speclflcpartsoftheCommlsslon's regulations, todelineate tach-nlouasusedbythestaffInevaluating speclflcproblemsorpostu-latedaccidents, ortoprovideguidancetoapplicants.

Regulatory Guidessrenocsubstitutes forregulations, andcompliance withthemIsnotrequired.

Methodsandsolutions different fromthosesatoutIntheguideswillbeacceptable Iftheyprovideabasisforthaflndlngsraaulslte tothoIssuanceorcontinuance ofapermitorlicensebytheCommlsslon.

ThisguidewasIssuedafterconslderatlon ofcommentsreceivedfcomthepublic.Cocnments sndsuggestions forImprovements Intheseguidesare'ncouraged atalltimes,andguideswillberevised,asappropriate, toaccommodate commentsandtoreflectnewInforma-tionoreccpecloncs.

CommentsshouldbesenttotheSecretary ofthsCommlsslor.

U.S.NuclearRegulatory Commlsslonh Washington, O.C.20555,,Attantlonc Docketing andServiceBranch.TheguidessraIssuedinthefollowing tenbroaddlvlslonsc 1.PowerReactors6.Products2,ResearchandTestReactors7.Transportation 3.FuelssndMaterials Facllltles 8.Occupational Health4.Environmental andSltlngg.Antitrust andFlnanclal Review5.Materials andPlantProtection 10.GeneralCopiesofIssuedguidesmaybopurchased stthecurrentGovernment pclntlngofficeprice.Asubscctptlon serviceforfuturoguidesInspo.elflcdlvlslons Isavallabls throughthoGovernment prlntlngOffice.Information onthesubscrlptlan socvlceandcurrentGpopricesmaybeobtainedbywrltlngthoU.s.NuclearRegulatory commlsslon, washington, D.c.20555,Attontlonc publlcatlons salesManager.

I~in1II+I TABLE1DESIGNANDQUALIFICATION CRlTERlAFORINSTRUNIENTATION Category1l.Equipment Qualification Theinstrumentation shouldbequaliTied inaccordance withRegulatory Guide1.89,"Qualification ofClasslEEquipment forNuclearPowerPlants,"andthemethod-ologydescribed inNUREG4588, "InterimStaffPosi-tiononEnvironmental Qualification ofSafety-Related Electrical Equipment."

Category21.Equipment Qualification SameasCategory1Category3l.Equipment Qualification Nospecificprovision Instrumentation whoserangesarerequiredtoextendbeyondthoserangescalculated inthemostseveredesign.basisaccidenteventforagivenvariableshouldbequali-fiedusingtheguidanceprovidedinparagraph 6.3.6ofANSI'.5.SameasCat<<g>>ry1Nosp<<<<ilicpn)vis')on Qualification appliestothecompleteinstrumentation channelfromsensortodisplaywherethedisplayisadirect-indicating meterorrecording device.Iftheinstru-mentation channelsignalistobeusedinacomputer-baseddisplay,recording, ordiagnostic program,qualifi-cationappliesfromthesensoruptoandincluding thechannelisolation device.SameasCategory1Nospccifi<<provision Theseismicportionofqualification shouldbeinaccor-dancewithRegulatory Guide1.100,"SeismicQualifica-tionofElectricEquipment forNuclearPowerPlants."Instrumentation shouldcontinuetoreadwithintherequiredaccuracyfollowing, butnotnecessarily during,asafeshutdownearthquake.

Nospecil'i<<provisi>>n Nospecilicprovision 2.Redundancy Nosinglefailurewithineithertheaccident-monitoring instrumentation, itsauxiliary supporting

features, oritspowersourcesconcurrent withthefailuresthatare2.Redundancy Nospecificprovision 2.Redundancy Nospecificprovision 4Coploaaroavallabla fromtheNRC/GPOSataaProgram,US.NuclearRegulatory Commlraion, Waahlnaton, D.C.20555.

2.(Continued)

Category1TABLE1(Continued)

Category2Category3acondition orresultofaspeciTicaccidentshouldpreventtheoperators frombeingpresented theinforma-tionnecessary forthemtodetermine thesafetystatusoftheplantandtobringtheplanttoandmaintainitinasafecondition following thataccident.

Wherefailureofoneaccident-monitoring channelresultsininforma-tionambiguity (thatis,theredundant displaysdisagree) thatcouldleadoperators todefeatorfailtoaccomplish arequiredsafetyfunction, additional information shouldbeprovidedtoallowtheoperators todeducetheactualconditions intheplant.Thismaybcaccomplished byproviding additional independent clrannels ofinformation ofthesamevariable(addition ofanidentical channel)orbyproviding anindependent channeltomonitoradifferent variablethatbearsaknownrelationship tothemultiplechannels(addition ofadiversechannel).

Redun-dantordiversechannelsshouldbeelectrically independ-entandphysicaHy separated fromeachotherandfromequipment notclassified important tosafetyinaccor-dancewithRegulatory Guide1.75,"Ph'ysical Independ-enceofElectricSystems,"

uptoand'including anyisola-!tiondevice.Withineachredundant divisionofasafetysysteni,redundant monitoring channelsarenotneededexceptforsteamgenerator levelinstrumentation intwo-loopplants.3.PowerSource3.PowerSource3.PowerSourceTheinstrumentation shouldbeenergized fromstationstandbypowersourcesasprovidedinRegulatory Guide1.32,"Criteria forSafety-Related ElectricPowerSystemsforNuclearPowerPlants,"andshouldbebackedupbybatteries wheremomentary interruption isnottolerable.

Theinstrumentation shouldbeenergized fromahigh-reliability powersource,notnecessarily standbypower,andshouldbebackedupbybatterieswheremomentary interruption isnottolerable.

Nospecificprovision Category1TABLE1(Continued)

Category2Category34.ChannelAvailability Theinstrumentation channelshouldbeavailable priorto!anaccidentexceptasprovidedinparagraph 4.11,"Excep-tion,"asdefinedinIEEEStd279-1971, "Criteria forPro-tectionSystemsforNuclearPowerGenerating Stations,"

orasspecified inthetechnical specifications.

4.ChannelAvailability Theout-of-service intervalshouldbebasedonnormaltechnical specification requirements onoutofserviceforthesystemitserveswhereapplicable orwherespecified byotherrequirements.

4.ChannelAvailability Nospecificprovision 5.QualityAssurance Regulatory Guide1.28"QualityAssurance PrograinRequirements (DesignandConstruction)"

Regulatory Guide1.30(SafetyGuide30)"QualityAssurance Require-mentsfortheinstallation, Inspection, andTestingofInstrumentation andElectricEquipment" Therecommendations ofthefollowing regulatory guidespertaining toqualityassurance shouldbefoUowed:5.QualityAssurance SameasCategorylas>>>odili<<d byth<<following:

Sincesomeinstru>nentatio<<

islessii>>purta>>t tosafetythanotherinstrumentation, itmaynotbenecessary toapplythesamequalityassurance measurestoallinstrumentation.

Thequalityassur-ancerequirements thatareimplemented shouldprovidecontroloveractivities affecting qualitytoanextentconsistent withtheimportance tosafetyoftheinstrumentation.

Theserequirements shouldbedetermined anddocumented bypersonnel knowl-edgeableintheenduseoftheinstrumentation.

5.QualityAssurance l1>ei>>stru>>>e>>Iationeliou1dbeoflugh-quality co>>>>>i<<rcial gra>leandshouldbeselectedtowithsta>>d thest>ecitied serviceenvironment.

Regulatory Guide1.38"QualityAssurance Require-mentsforPackaging,

Shipping, Receiving, Storage,andHan-dlingofItemsforWater-Cooled NuclearPowerPlants"Regulatory Guide1.58"Qualification ofNuclearPowerPlantInspection, Examination, andTestingPersonnel" Regulatory Guide1.64"QualityAssurance Require-mentsfortheDesignofNuclearPowerPlants"Regulatory Guide1.74"QualityAssurance TermsandDefinitions" 5.(Continued)

Category1TABLE1(Continued)

Category2Category3Regulatory Guide1.88"Collection, Storage,andhfain-tenanceofNuclearPowerPlantQualityAssurance Records"Regulatory Guide1.123"QualityAssurance Require-mentsforControlofProcure-mentofItemsandServicesforNuclearPowerPlants"Regulatory Guide1.144"Auditing ofQualityAssurance ProgramsforNuclearPowerPlants"IOORegulatory Guide1.146"Qualification ofQualityAssur-anceProgramAuditPersonnel forNuclearPowerPlants"Reference totheaboveregulatory guides(exceptRegula-toryGuides1.30and1.38)isbeingmadependingissuanceofarevisiontoRegulatory Guide1.28thatisunderdevel-opment(TaskRS002-5)andthatwillendorseANSI/AShIE NQA-I-1979,"QualityAssurance ProgramRequirements forNudearPowerPlants."6.DisplayandRecording Continuous real-time displayshouldbeprovided.

Theindication maybeonadial,digitaldisplay,CRT,orstripchart recorder.

Recording ofinstrumentation readoutinformation shouldbeprovidedforatleastoneredundant channel.6.DisplayandRecording Theinstrumentation signalmaybedisplayed onanindividual instrument oritmaybeprocessed fordisplayondemand.Signalsfromeffluentradioactivity monitorsandareamonitorsshouldberecorded.

6.DisplayandRecording SameasCategory2Signalsfromeffluentradioactivity

monitors, areamonitors, andmeteorology monitorsshouldberecorded.

5QopteamayheobtainedfromtheAmericanSocietyofMechanical Engineers, 345East47thStreet,NewYork,NewYo<<teet7.

TABLE1(Continued)

Category2Category36.(Continued)

Ifdirectandimmediate trendortransient information isessential foroperatorinformation oraction,therecording shouldbecontinuously avaBableonredun-dantdedicated recorders.

Otherwise, itmaybecon-tinuously updated,storedincomputermemory,anddisplayed ondemand.Intermittent displayssuchasdataloggersandscanningrecorders maybeusedifnosignificant transient responseinformation islikelytobelostbysuchdevices.SameasCategory1SameasCategory17.RangeIftwoormoreinstruments areneededtocoveraparticular range,overlapping ofinstrument spanshouldbeprovided.

Iftherequiredrangeofmoni-toringinstrumentation resultsinalossofinstru-mentation sensitivity inthenormaloperating range,separateinstruments shouldbeused.7.RangeSalileasCategoryl7.ltaugeSeineasCategory18.Equipment Identification TypesA,B,andCinstruments designated asCate-gories1and2shouldbespecifically identified withacommondesignation onthecontrolpanelssothattheoperatorcaneasilydiscernthattheyareintendedforuseunderaccidentconditions.

8.Equipment Identification SameasCategory18.Equipment Identification Nospecificprovision 9.Interfaces Thetransmission ofsignalsforotheruseshouldbethroughisolation devicesthataredesignated aspartofthemonitoring instrumentation andthatmeettheprovisions ofthisdocument.

10.Servicing, Testing,andCalibration Servicing, testing,andcalibration programsshouldbespecified tomaintainthecapability ofthemonitoring instrumentation.

Iftherequiredintervalbetween9.Interfaces SameasCategoryI10.Servicing, Testing,andCalibration SameasCategory19.Interfaces Nospecificprovision 10.Servicing, Testing,andCalibration SameasCategoryI 10.(Continued)

Category1TABLE1(Continued)

Category2testingislessthanthenormaltimeintervalbetweenplantshutdowns, acapability fortestingduringpoweroperation shouldbeprovided.

Whenevermeansforremovingchannelsfromserviceareincludedinthedesign,thedesignshouldfacilitate administrative controloftheaccesstosuchremovalmeans.SameasCategory1SameasCategory1Thedesignshouldfacilitate administrative controloftheaccesstoallsetpointadjustments, modulecalibra-tionadjustments, andtestpoints.SameasCategory1SallleasCategory1Periodicchecking, testing,calibration, andcalibration verification shouldbeinaccordance withtheapplicable portionsofRegulatory Guide1.118,"Periodic TestingofElectricPowerandProtection Systems,"

pertaining totestingofinstrument channels.

(Note:Responsetimetestingnotusuallyneeded.)SameasCategoryISameasCategory1Thelocationoftheisolation deviceshouldbesuchthatitwouldbeaccessible formaintenance duringaccidentconditions.

SameasCategory1Nospecificprovision 11.HumanFactorsTheinstrumentation shouldbedesignedtofacilitate therecognition,

location, replacement, repair,oradjustment ofmalfunctioning components ormodules.11.HumanFactorsSameasCategory111.HumanFactorsSameasCategory1Themonitoring instrumentation designshouldminimizethedevelopment ofconditions thatwouldcausemeters,annunciators, recorders, alarms,etc.,togiveanomalous indications potentially confusing totheoperator.

Humanfactorsanalysisshouldbeusedindetermining typeandlocationofdisplays.

SameasCategory1SameasCategory1 11.(Continued)

Category1TABLE1(Continued)

Category2Category3'ITotheextentpracticable, thesameinstruments shouldbeusedforaccidentmonitoring asareusedforthenormaloperations oftheplanttoenabletheoperators touse,duringaccidentsituations, instruments withwhichtheyaremostfamiliar.

SameasCategoryISameasCategory112.DirectMeasurement Totheextentpracticable, monitoring instrumentation inputsshouldbefromsensorsthatdirectlymeasurethedesiredvariables.

Anindirectmeasurement shouldbemadeonlywhenitcanbeshownbyanalysistoprovideunambiguous information.

12.DirectMeasurement SameasCategoryl12.DirectMeasurement SameasCaltcgofy l

TABLE3PWRVARIABLES TYPEAVariables:

thosevariables tobemonitored thatprovidetheprimaryinformation requiredtopermitthecontrolroomoperatortotakespecificmanuallycontrolled actionsforwhichnoautomatic controlisprovidedandthatarerequiredforsafetysystemstoaccomplish theirsafetyfunctions fordesignbasisaccidentevents.Primaryinformation isinforma-tionthatisessential forthedirectaccomplishment ofthespecified safetyfunctions; itdoesnotincludethosevariables thatareassociated withcontingency actionsthatmayalsobeidentified inwrittenprocedures.

AvariableincludedasTypeAdoesnotprecludeitfrombeingincludedasTypeB,C,D,orEorviceversa.VariablePlantspecificRangePlantspecificCategory(seeRegulatory Position1.4andTable1)Information requiredforoperatoractionTYPEBVariables:

thosevariables thatprovideinformation toindicatewhetherplantsafetyfunctions arebeingaccomplished.

Plantsafetyfunctions are(I)reactivity control,(2)corecooling,(3)maintaining reactorcoolantsystemintegrity, and(4)maintaining containment integrity (including radioactive effluentcontrol).

Variables arelistedwithdesignated rangesandcategoryfordesignandqualification requirements.

Keyvariables areindicated bydesignandqualiTication Categoryl.Reactivity ControlNeutronFlux10%to1007ofullpowerFunctiondetection; accomplishment ofmitigation ControlRodPositionRCSSolubleBoronConcen-trationFullinornotfullin0to6000ppmVerification Verification RCSColdLegWaterTemper-ature50Fto400FVeriTication CoreCoolingRCSHotLegWaterTemper-ature50Fto700FFunctiondetection; accomplishment ofmitigation; verification; long-term surveillance RCPColdLegWaterTemper-50Fto700FaturerFunctiondetection; accomplishment ofmitigation; veriTication; long-term surveillance RCSPressure0to3000psig(4000psigforCEplants)200Fto2300F1233Functiondetection; accomplishment ofmitigation; veriTication; long-term surveillance VeriTication IWhereavariabioislistedformorathanonepurpose,theinstrumentation raqulrarnants mayboIntegrated andonlyonomaasuramont provided.

2ThemaxhnumvaluemayberavisadupwardtosatisfyATWSroquiramants.

3Instrumentation thatIsapartofthellnalICCdatactlon systomshouldmeetthedesignroqulramonts spadflodlnItamILF.2 ofNUREG<737.

(NthanTypoKtharmocouptas bacomopartofthosystam,thayaroconsidarad tomoottheraqulromants.

Howovar,thoromaindar ofthodataction systemthatisoutsidothereactorvassalshouldmootthoraqulromants spadflod.)

1.97-22 TABLE3(Continued)

RangeCategory(seeRegulatory Position1.4andTable1)TYPEC(Continued)

FuelCladding(Continued)

Radioactivity Concentration orRadiation LevelinCirculating PrimaryCoolantAnalysisofPrimaryCoohnt(GammaSpectrum) 1/2TechSpeclimitio100timesTechSpeclimit10pCi/mlto10Ci/mlorTID-14844 sourcetermincoolantvolume36Detection ofbreachDetailanalysis; accomplishment ofmitigation; veriTication; long-term surveillance ReactorCoolantPressureBoundaryRCSPressureIContainment Pressurel 0to3000psig(4000psigforCEplants)-5psigtodesignpressure4(-10psigforsubatmospheric containments) 12Detection ofpotential fororactualbreach;accomplishment ofmitiga-tion;long-term surveillance Detection ofbreach;accomplishment ofmitigation; verification; long<ermsurveillance Containment SumpWaterLeveliNarrowrangetoptobottom(sump),widerange(plantspecific)

Detection ofbreach;accomplishment ofmitigation; verification; long-term surveillance EffluentRadioactivity

-NobleGasEffluentfromCondenser AirRemovalSystemExhaust10pCi%cto10pCi%cContainment AreaRadiation 1R/hrto10R/hr37,839Detection ofbreach;verification Detection ofbreach;verification Containment RCSPressureI0to3000psig(4000psigforCEplants)Detection ofpotential forbreach;accomplishment ofmitigation SampUngormonitoring ofradioactive Uquidsandgasesshouldbeperformed inamannerthatensuresptocutement oftepesentative samoles.ForeasesthecriteriaofANSIN13.1.1969, "G>>udetoSamplingAitbotnoRadioactive Materials inNuclearFacUiiies>'hould beappQed.Forllquih,provisions shouldbemadeforsamplingfromwell.mixedturbulent zones,andsamplinglinesshouldbede>>dgnedtomlnl-nJoplateoutordeposition.

Forsafeandconvenient sampgng,theprovisions shouldindude:a.Shielding tomaintainradiation dosesALARA,b.Samplecontainers withcontalnetmmpUng portconneciot compatibility, c.Capabigiy ofsamplingunderprimarysystempressureandnegativepressures, d.HandUngandtransport capability, ande.Prearrangement foranalysisandmietpteiailon.

7Mlnhnumofiwomonitorsatwidelyseparated locations.

8Detectors shouldrespondiogammaradiation phoionswithinanyenergyrangeftom60koVto3MoVwithadosetatoresponseaccuracywithinafactorof2overtheeniitorange.9Monitorsshouldbecapableofdetecdngandmeasuring gaseouseffluentradioactivity withcompositions tanyngfromfreshequlUbtlutn noblegasladonProductmixturesioiordayrold

mixtures, withoverallsystemaccuracies,within afactorof2.Effluentradioactivity maybo<<p<<ssodlntermsofconcentrations ofXe-133equivalents, intermsofconcentrations ofanynoblegasnucUdes,orintermsofintegrated naMeVpetunItthno.Itisnotexpectediha!asinglemonitoring devicewillhavesuNcienttangotoencompass theoafltetangoprovidedthisregulatory guideandthatmulilolocomponents orsystemswillbeneeded.Existingequlpmoat maybeusedtomonitoranyportionofihstatedtangowitidntheequipment designrating.r1.97-24 Attachment 4toAEP:NRC:0856T Reasonsand10CFR50.92AnalysisforChangetotheDonaldC..CookNuclearPlantUnitNos.1and2Technical Specifications Illr~~\Attachment 4toA:NRC:0856T Page1Containment WaterLevelMonitorIIF1.5TheguidancegiveninGenericLetterNo.83-37statesthat:~"Acontinuous indication ofcontainment waterlevelshouldbeprovidedinthecontrolroomofeachreactorduringPowerOperation, StartupandHotStandbymodesofoperation.

Atleastonechannelfornarrowrangeandtwochannelsforwiderangeinstruments shouldbeoperableatalltimeswhenthereactorisoperating inanyoftheabovemodes.Narrowrangeinstruments shouldcovertherangefrombottomtothetopofthecontainment sump.Widerangeinstruments shouldcovertherangefromthebottomofthecontainment totheelevation equivalent toa600,000gallon(orlessifjustified) capacity.

"Technical Specifications forcontainment waterlevelmonitorsshouldbeincludedwithotheraccidentmonitoring instrumentation inthepresentTechnical Specifications.

LCOs(including therequiredActions)forwiderangemonitorsshouldincludetherequirement thattheinoperable channelwillberestoredtooperablestatuswithin30daysortheplantwillbebroughttoHotShutdowncondition asrequiredforotheraccidentmonitoring instrumentation.

Typicalacceptable LCOandsurveillance requirements foraccidentmonitoring instrumentation areincludedinEnclosure 3."kWeareproposing thatT/STables3.3-11and3.3-10forUnits1and2,respectively, berevisedtoincludetherequirement thatatleasttwocontainment waterlevelchannelsandonecontainment sumplevelchannelbeoperableduringModes1,2,and3.Inaddition, weareproposing thatT/STables4.3-7and4.3-10forUnits1and2,respectively, berevisedtoincludethesurveillance requirements forthesechannels.

Inordertofollowtheaboveguidance, andmaintaininternalconsistency withourcurrentTechnical Specifications, the30-dayactionstatement inT/S3.3'.8forUnit1and3.3'.6forUnit2isproposedforthecontainment waterlevelandcontainment sumplevelinstrumentation.

TheformatofT/STables3.3-11and3.3-10forUnits1and2variesfromtheGenericLetterexamplebecauseourpresentT/Ssincludeonlyonecolumnlisting"MinimumChannelsOperable."

Inordertokeeptheformatsimilartootheraccidentmonitoring instrumentation includedinthepresentT/Ss,thecolumnlistingthe"Required No.ofChannels" isnotincluded.

Per10CFR50.92,aproposedamendment willnotinvolveasignificant hazArdsconsideration iftheproposedamendment doesnot:(1)involve'significant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, (2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluated, or(3)involveasignificant reduction inamarginofsafety.

lN~P7Attachment 4toA..NRC:0856T Criterion Thesechangeswillexpandthelicenserequirements forpost-accident monitoring instrumentation andassisttheoperatorinrecovering fromanaccident.

Thechangeswillnotinvolveasignificant increaseintheprobability orconsequences ofanypreviously evaluated accident.

Criterion 2Thechangesdonotaffectnormaloraccidentplantoperation.

Inanaccidenttheywillservetoprovidedatatotheoperator; therefore, thechangeswillnotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously analyzedorevaluated.

Criterion 3Thechangesdonotinvolveasignificant reduction inthemarginofsafety,sincetheywillonlyrequirethatadditional databeavailable totheoperator.

TheCommission hasprovidedguidanceconcerning thedetermination ofsi.gnificant hazardsbyproviding certainexamples(48FR14870)ofamendments considered notlikelytoinvolvesignificant hazardsconsideration.

Thesecondoftheseexamplesreferstochangesthatimposeadditional limitations, restrictions, orcontrolsnotpresently includedintheT/Ss.Sincetherequirement forsumpandcontainment waterlevelmonitorsconstitute arestriction whichthecurrentT/Ssdonothave,webelievethisexampleisapplicable andthatthechangesinvolvenosignificant hazardsconsideration.

TheaboveT/Schangesconstitute additional restrictions tothepresentT/Ss.Therefore, webelievethatthesechangesdonotinvolveasignificant hazardsconsideration asdefinedin10CFR50.92.ItisnotedthatAEP:NRC:0856I alsoproposedchangesfortheaxialpowerdistribution monitoring systemandseveraladministrative changes.Wearelimitingthissubmittal tochangesforthecontainment waterlevelandcontainment sumplevelinstrumentation.

Werequestthatyourstaffcontinuetoreviewthechangesregarding theaxialpowerdistribution systemandtheadministrative changesassubmitted inAEP:NRC:0856I.

~~tt!