ML17320A814
| ML17320A814 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/04/1983 |
| From: | ALEXICH M P INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | EISENHUT D G Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0838A, AEP:NRC:838A, GL-83-28, NUDOCS 8311110162 | |
| Download: ML17320A814 (80) | |
Text
p)~REGULATOINFORMATION DISTRIBUTION TEM(RIDS)AUTH~NAME,AUTHORAFFILIATION ALEXICH<M
~REIndiana'5MichiganElectricCo,RECIP~NAMESRECIPIENT AFFIL'IATION EISENHUT<D>G.
DivisionofLicensing
SUBJECT:
ForwardsrTesPonse "toGenerfc,,Ltr8328r"RequfredActionsBasedonGenericImplications ofSalemATNSEvents,."
Vendordocumentcontrol>sysestablished 8programwillbe;inplaceb)endof1985,DISTRISUTXON CODE:A001SCOPIESRECEIVED:LT'R
.j'iENCLLSIZEA'J'ITLEcORSubmfttal:GeneralDistributfon-NOTES!ACCESSION NBRt8311110162'OC
~DATES83/11/00NOTARIZED:
YESDOCKETFACIL:50315DonaldCCookNuclearPowerPlenty'UnftigIndiana80500031'5
- 50316DonaldC<CookNuclearPowerPl-antgUnft2gIndianaL05000316RECIPIENT
=IDCODE/NAME NRRORBiBC01INTERNALO ELD/HDS3NRR/DLDIRNRRETBEGIL'EOQ'COPIES,l"TTRENCL'701111RECIPIENT IDCODE/NAME NRR/DE/MTEB NRR/DL/DRAB NRR/DSI/RABRGN3COPIESLTTRENCL1i.1"011EXTERNAL'CRS NRCPDRNTIS0902'61111LPDRNSIC-03-052211'TOTALNUMBEROFCOPIESREQUIREDS LTTR26ENCL24 g~lksc')Fp<)c)c4r-;nr,r'onef"c~nr"inI""~)I3'>><TAT,c,<
')I>>.','v,".><~L',>i)~~)3940,"'i),f3~Pr'X)Lhd>4;,.jlAn.)>>c)"..il~tTf3kH:S4i,k".I,'~I).)At9m))inc.l0")~<n"casyf>up~~pc'),Juf<,nyct'I'c",ll)A3Jrn<!i$'ngt~3I'9to>1srDell>8~4)~J9rcine)c!6I8.rIT~)A.pJor~9ooflnr~~h<<ar~~ArnorbnI,'l.~'3,831X.].3APOITAT)J4~><1<<vL'<I))~)j"'4A,')I')
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~)~~ui)aiHHR'<AAXIcr)NRHN Q~8,)Q$013c)r INDIANA8MICHIGANELECTRICCOMPANYP.O.BOX16631COLUMBUS, OHIO43216November4,1983AEP:NRC:0838A DonaldC.CookNuclearPlantUnitNos.1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74GENERICLETTER83-28REQUIREDACTIONSBASEDONGENERICIMPLICATIONS OFSALEMATWSEVENTSMr.DarrelG.Eisenhut, DirectorDivisionofLicensing, NRCU.S.NuclearRegulatory Commission Washington, D.C.20555
DearMr.Eisenhut:
ThisletterisinresponsetoGenericLetter83-28ofJuly8,1983whichrequiredactionsbasedongenericimplications oftheAntici-patedTransient WithoutScram(ATWS)incidentatSalem.Owingtothelevelofdetailassociated withtheseresponses, wehaveincludedthemasanattachment ratherthanin'hebodyoftheletteritself.Verytrulyyours,M..AlchiIgVicePresident Attachment cc:JohnE.DolanW.G.Smith,Jr.-BridgmanR.C.CallenG.CharnoffE.R.Swanson,NRCResidentInspector
-Bridgman8311110162 831104PDRADOCK05000315PPDRi STATEOFOHIOFRANKLINCOUNTYAEP:NRC:0838A MiltonP.Alexich,beingdulysworn,deposesandsaysthatheistheVicePresident ofLicenseeIndiana6MichiganElectricCompany,thathehasreadtheforegoing letterandtheAttachment (AEP:NRC:0838A ResponsetoGenericLetter83-28,RequiredActionsBasedonGeneric,Implications ofSalemATWSEvents)andknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledge andbelief.Milon.AlexiSubscribed andsworntobefore'ethisfourthdayofNovember, 1983.g~~g,gem~NotaryPublicROBERTA.,DhgLDy~
NOTARYpOOl.l.,pRpp)(@l;OOUNTY,'Hl0 COMMISSION F.'iPlRES
@GUST'~1p Aj'IgI ATTACHMENT TOAEP:NRC:0838A RESPONSETOGenericLetter83-28REQUIREDACTIONSBASEDONGENERICIMPLICATIONS OFSALEMATWSEVENTS
(
1.POSTTRIPREVIEWProgramDescritionandProceduxe Presently, attheD.C.CookPlant,administrative procedures requireallshiftsupervisors tonotifythePlantManagement ofareactortriporofanysignificant operational events.PlantstartupiscoveredbyOperating Procedures whichrequirethatthePlantManager's concurrence beobtainedpx'iortorestart.Inhisabsence,thisresponsibility isassumedbytheAssistant PlantManager(operations) ortheAssistant PlantManager(maintenance)
.Thebasisfordetermining thatarestartisacceptable isthatthecauseoftheunplanned triphasbeendetermined andcorrected andthattheplantreacted"normally."
Intheeventthatthecauseofthetx'ipcannotbedetermined, theShiftSupervisor mustdetermine thatreactoroperation canproceedsafely(i.e.,theprotective andtripsystemsarefullyfunctional)
.PlantManagerordesigneeapprovalisxequiredforallreactorrestarts.
Wearepresently developing areactorpost-trip reviewprocedure whichwillbeusedtoassessthereadiness oftheunittosafelyreturntopowex'.Thisprocedure willembodymanyoftherecommendations ofINPO'sGoodPractice, OP-2llgPostTripReviewprocedure.
Extensive useofSignOffSheetsandplantstatusloggingisbeingbuiltinsothattheplanthistoryaroundthetimeoftripcanbedetermined forfutureanalysis,
- trending, andbacktracking.
Afirstdraftofthenewprocedure hasbeenreviewedbythePlantandAEPengineering personnel.
Commentsarepresently beingevaluated.
Itisestimated thattheseconddraftwillbeavailable forreviewbyJanuary1,1984,andtheapprovedprocedure issuedbyMarch30,1984.RestartCriteriaPresentrestartcriteriaarecoveredabove.Thepost-trip reviewprocedure willincludecriteriaformakingthedecisiontorestart.Resnsibilit/Authority Thepersonnel involvedwiththereviewandanalysisoftheeventsleadingtothetripandrestartaretheOperator, ShiftTechnical Advisor,ShiftSupervisor, Superintendent ofOperations, Assistant PlantManagers, andthePlantManager.
Ir ualifications/Trainin Allpositions referenced intheprocedure meetthequalification requirements ofTechnical Specification, Section6.3,FacilityStaffQualifications.
TheShiftSupervisors, Operations Superintendent, andtheAssistant PlantManager(Operations) holdSROlicenses.
Detailedqualifications ofalllicensedincumbents havebeenpreviously transmitted totheNRC.Wecanprovidethesedetailsifrequested.
SourcesofInformation Item1.2(PostTripReview-DataandInformation Capability) providesdetailsoftheinformation available tooperating personnel.
ThenewPostTripReviewProcedure willformalize thepracticeofrecording datarelatingtothetrip.Itisanticipated that,oncefinalized, thepost-trip reviewdatapackagewillberetainedforfuturereference.
EventAnalsisThereisnoformalorwrittencriteriaforcomparing the"tripasoccurred" versusthe"tripaswouldhavebeenpredicted" inaquantitative sense.However,thePlanthasinformation detailedinSection1.2torelyoninthismatter.Independent ReviewThePlantManagerhasthefreedomtoaskforanindependent assessment ofanyunplanned trip.Insuchcases,heisabletocallfortheadviceandassistance oftheAmericanElectricPowerServiceCorporation.
Thefirstpersonhewouldnormallycontactforsuchassistance istheVicePresident, NuclearEngineering, althoughhewouldbefreetocontactanymemberoftheNuclearSafetyDesignReviewCommittee oranymemberoftheServiceCorporation thathethoughtappropriate tosolvetheproblemathand.Ifcontactwithoutsidevendorswasrequired, thiswouldnormallybedoneafterappropriate consultation betweenthePlantManagerandAEPSC.Thereisnoformalwrittencriteriafortakingsuchanaction.ThePlantNuclearSafetyReviewCommittee willreviewalleventspriortorestartifthecauseofthereactortripisnotpositively knownoriftheplantresponsedemonstrated anabnormalbehaviorthathasnotbeencorrected.
Theexistingrestartprocedure ensurestherecording ofbasicinformation.
ThenewPostTripReviewP-ocedure willextendthescopeandprovidemoredetailedguidanceastowhatdataneeds.tobesaved.
ll 1.2DataandInformation Capabilit Thefollowing writeupidentifies themonitoring systemsinstalled inUnitl.Identical monitorsareinstalled inUnit2andmonitorthesamedevicesexceptforthedifferences betweentheUnit1andUnit2turbines.
A.Hathawa0erationsSequenceMonitor.1.2.1.1.Thesequencemonitorprovidesaprintedrecordoftheoperation ofcertainselectedevents.Ithasthecapacitytomonitor192on-off.pointsandproducesalineitemoutputonaprinterlocatedinthecontrolroomwhenanyoneofthemonitored pointsindicates anabnormalcondition.
1.2.1.2~Forty-five pointsareusedtomonitoreventsrelatedtoreactortripinitiation orreactortripcircuitbreakerposition, 6pointsmonitorcondensate orhotwellpumps,13pointsmonitorfeedwater heaterextremehighlevelevents,6pointsmonitoronsitepowerdieselgenerators, 22pointsmonitorthemainfeedwater pumps,40pointsmonitorthemainturbine-generator, and8pointsmonitorthestep-upandauxiliary transformers andmiscellaneous items.1.2.1.3Theoperations sequencemonitorpermitsdiscrimination forcontactclosureswhichoccurmorethan2milliseconds apart.1.2.1.4~Acontactclosurewillresultinalineitemprintoutonadedicated printerlocatedinthecontrolroom.Thelineitemcontainsa3digitnumberforthedayoftheyear,a4digitnumberforthehourandminute,a2digitnumberforthesecond,a3digitnumberforthemilliseconds, an"A"indicating anoffnormalcondition, a3digitnumbertoidentifytheindividual inputpoint,andapreprogrammed legendofapproximately 22characters maximumtoidentifytheeventtotheoperator.
1.2.1.5.Theprinteroutputsheetsmayberetainedforfutureuse.1.2.1.6.Theoperations sequencemonitorispoweredfromabalanceofplant(nonclassIE)inverter.
B.Esterline AngusTurbineEventMonitor.1.2.1.1.Theturbineeventmonitorisadual-unit stripchartrecorder.
Eachofthe2chartshas20on-offpoints.Thespeedofthecontinuously movingchartsischangedafteratripinitiation sothat24hoursofchartareadvancedthroughtherecorderin24seconds.Thechartspeedthenreturnstonormaluntilallinitiating eventshavereturnedtonormalandatripinitiation eventrecurs.1.2.1.2~Twopoints,oneoneachchart,areusedtoindicateoperation ofanytripinitiation event.Thesepointsareusedtosynchronize the2charts.Twopointsareusedtomonitorthe I14 TrainAandTrainBreactortripcircuitbreakers, 2pointsmonitorelectrical lockoutrelayswhichindicateanelectrical systemleveltrip,and16pointsmonitorthepositionofturbineemergency andpre-emergency valves(stopandinterceptor valves).Theremaining pointsmonitorvariousturbinetripinitiating events.1.2.1.3.Thetimediscrimination betweeneventsisapproximately 20milliseconds whenthechartisinhighspeedoperation.
1.2.1.4.Thedataisdisplayed on2stripcharts.Eachpointoperatesaheatpenwhichleavesacontinuous traceonthethermally sensitized chart.Thepenstraceaprintedlineonthecharttoindicateanormalcondition.
Thepenmovesofftheprintedlinetoapositionapproximately midwaybetweentheprintedlinesfor2adjacentpointstoindicateanoffnormalcondition.
1.2.15.Thechartsformapermanent recordandmayberetainedforfuturereference.
1.2.1.6.Thesolenoids whichoperatethepointpositioning mechanisms arepoweredfromoneofthestationbatteries.
Thechartdrivemechanism ispoweredfromthebalanceofplant(nonclassXE)inverter.
C.HathawaOscilloraph.1.2.1.1Theunitoscillograph has32galvanometers.
Eachgalvanometer willrecordoneanalogchannelor,ifproperlymodified, 4on-offfunctions.
Eightgalvanometers havebeenconverted toon-offfunctions andtheremaining galvanometers arereservedforelectrical analogquantities.
Theunit,hasaprefaultrecording featurewhereallinputquantities arecontinuously recordedonamagneticdisc.Undernormalconditions, thedataareerasedandcurrentrecordings writtenovertheoldspaceafterapproximately 100milliseconds.
Ifoneofaspecificsetofeventsoccurs,thedataarerecordedonultra-violet sensitive photographic papersuchthattheinformation recordedpriortotheeventisrecorded, followedbyadditional dataresulting fromtheevent.Therecording iscontinued forafixedtimeperiodfollowing theevent.Recording chartspeedmaybeselectedtobeeither12"or3"persecond,theusualpracticebeingtorecordtheinitialportionoftheeventatthehigherchartspeedfollowedbyadditional recording attheslowerchartspeed.1.2.1.2~SixpointsareusedtomonitortheAandBtrainreactortripcircuitbreakerpositions, undervoltage tripinitiation, andsafetyinjection actuation; 2pointsmonitorthestartofonsitepowerdieselgenerators; 1pointmonitorsthetripof 1C!
thefeedwater pumps;10pointsmonitorturbine-initiated events;7pointsmonitorgenerator andexcitation events;and4tracesareusedforreferences toassistinidentification oftracelocations.
Theanalogtracesrecordgenerator phasecurrents, phaseandgroundvoltages, andfieldcurrent.Thetimediscrimination betweeneventsduringhigherchartspeedisbetterthan5milliseconds
.betweeneventsandbetterthan10milliseconds duringslowerchartspeed.Thedisplayprovidedbythedeveloped photographic paperis'areproduction oftheamplitude andwaveshapesoftheanalogelectrical quantities.
Theon-offeventsareindicated byacontinuous straightlinetraceforanormalcondition ortheabsenceofthetraceatthatlocation, signifying anoffnormalevent.Thephotographic paperisdeveloped byexposuretoultra-violet light(fluorescent lightsareadequatesources),
andnowetchemicalpiocesses arerequired.
Thephotographic paperrecordmayberetainedforfuturereference provideditisnotcontinuously exposedtosunlightorfluorescent lights.Thesolenoids fortheon-offeventdevicesarepoweredfromoneofthestationbatteries.
Theremaining powernecessary tooperatetheoscillograph andaccessory equipment isthebalanceofplant(nonclassZE)inverter.
Thecomplement ofprogramsfortheP250processcomputerincludestwoprogramswhicharerelevanttotheanalysisofreactortrips.ThesetwoprogramsarethePostTripReviewProgramandtheSequenceofEventsRecording Program.TheSequenceofEventsRecording Programrecordsthesequenceofoperation ofanumberofmonitored contactstoahightimeresolution.
Whenoneofthemonitored
.contacts changesstate,aninterrupt isinitiated whichcausestheP250toscaneachmonitored contactforanychangefromitspreviousstate.Theprogramstoressuchchangesandthecyclecountsincethefirstevent.Acycleianominally l6.7milliseconds inlength.Duetoadead4imeof2milliseconds intheinterrupt process,anautomatic rebidoftheprogramisprogrammed forthecyclefollowing eachinterrupt bid.Thisisdonetoavoidlossofcontactchangesduringthedeadtime.TheSequenceofEventsRecording Programisterminated wheneitherthecyclecountreaches3600or25contactchangeshavebeenrecorded.
Whentheprogramisterminated, anoutputroutineiscalled.Allcollected dataarefirstmovedtotheoutputprogrambufferstofreetheSequenc'e ofEventsRecording Programbuffersforcontinued monitoring.
Theoutputroutineprintsthetimeofthefirsteventinhours,minutes,andseconds.Following thismessage,thealpha-numeric address,a36-character contactdescription, andcyclecountfromthefirsteventareprintedforeachcontactchange.Thefirsteventwillalwayshaveacyclecountof'ero.TheP250addresslistindicates thatthereisaninputtotheSequenceofEventsRecording Programforeachpotential reactortrip.Znthecaseofreactorcoolantpumpunderfrequency, partialtripsarealsoincluded.
Enaddition, thereactortripandreactortripbypasscircuitbreakers, maingenerator outputcircuitbreakers, andturbinestopvalvesaremonitored.
Thetimediscrimination betweeneventsisonecycleornominally 2.0milliseconds.
Theformatfordatadisplayisdiscussed aboveinthedescription oftheprogram..
ThedataisoutputononeoftheP250typewriters.
Theprinteroutput,sheetsmayberetainedforfuturereference.
TheprimarypowersourcefortheP250computerisaninvertersuppliedbytheABbatteryand600voltbusllB.Zftheinvertershouldfail,theP250computerwouldbeswitchedbyanautomatic bustransfertothecontrolroompowerdistribution circuit,CRP-3,whichissuppliedfromtheplantlightingtransformer.
Thepowersourceisbalanceofplant(nonclassZE).
I ThePostTripReviewprogramperiodically recordsanumberofpre-selected inputs.Theseinputsarestoredonadiscinacircularbuffer,withnewersetsofdatareplacing
-theoldersets.Whenatripoccurs,eitherautomatically (PostTrip)ormanually(TestTrip),thepre-tripdatabeingenteredintothecircularbufferare.frozenandthedataarethereafter storedinapost-trip buffer.Whenthisbufferisfilled,bothsetsofdata(preandpost)areprintedoutonthetypewriter.
Theparameters monitored areanaloginnature.Theywouldnormallyincludesteamgenerator feedwater flowandsteamflow,steam.generator narrowrangeandwiderangelevel/pressurizer level,pressurizer levelsetpoint, sourcerangedetectoroutput,intermediate rangedetectoroutput,powerrangedetectoroutput,first.stageturbinepressure, steamgenerator
- pressure, pressurizer
- pressure, containment
- pressure, unit,grosselectrical output,Taverage, deltaTpower,.overtemperature deltaTsetpoint, overpower deltaTsetpoint, widerangecoldlegtemperatures, pressurizer steamtemperatures, T-reference, auctioneered deltaT,andauctioneered Tavg.Theseparameters remainasselectedbythecomputervendor,Westinghouse ElectricCorporation.
Eightoftheparameters inthepreviousparagraph aresampledat2-secondintervals, 6secondsbeforeandafterthetrip.ThesearetotalNISpowerrangepower,turbinefirststagepressure, unitgrosselectrical output,andauctioneered Taverage.
Allparameters aresampledat8-secondintervals for2minutesbeforeand3minutesafterthetrip.Thesesamplingtimesremainassetbythecomputervendor.ThePostTripPrintprogramfirstoutputsastartmessageontheappropriate typewriter.
Itthenoutputsalineofheadingsforthevalueswhichwillbeprintedincolumnarform.Theheadingsconsistofthesix-character nameofthepoint.Thevaluesareprintedbelowtheir'names,startingwiththeoldestsetofdataonthefirstline,thenextoldestonthenextline,andsoonuntilthemostrecentpre-tripdataareprinted.Includedineachrowofdataisacolumnindicating thetime.Whenallthepre-tripdataforthis.setofpointsareprinted,themessagePOSTTRIPDATA-TRIPTIMEXXXXisprinted.Allthepost-trip forthesepointsareprintedinthesameformatasdescribed above.Afterallthepost-trip dataforthesepointsarefinished, theprogramstartsoverwithanothersetofdatainthesameformat:6character names,pre-tripvalues,tripmessage,andpost-trip values.Whenallthepointshavebeenprinted,theprogramoutputsafinishedmessage,unblocksthecollection
- programs, andexits.
Fromtimetotimeotheranalogvaluesmaybesubstituted for~theidentified quantities to'implement investigations ofanomalous behaviorofothersystemsorcomponents.
Thediscussion ofdataretention andpowersourcefortheSequenceofEventsRecording programalsoappliestothePostTripReviewprogram.
PklI 1.2'Inadditiontothedatacollection previously mentioned, theinformation contained onthefollowing stripchartrecorders wouldassistinresolving orreconstructing theeventssurrounding areactortrip.RCSWideRangeLoopTemperature HotandColdLegRecorder(4)Reference TavgTemperature
-Auctioneered TavgTemperature RecorderControlBankandInsertion Limits,RecorderNuclearInstrumentation Recorder(7)MainSteam,MainFeedwater FlowandSteamGenerator LevelRecorder(4)FeedpumpSuctionandDischarge PressureRecorderMainTurbineVibration RecorderkFeedPumpTurbineVibration RecorderIMainSteamPressureRecorder(2)FirstStagePressureRecorder(2)Pressurizer LevelRecorderPressurizer PressureRecorderComputerTrendingRecorder(2)Wide'RangeReactorCoolantPressureRecorderContainment PressureRecorder(2)Thepreceding isnotalistin'gofallrecorders available, butisalistingofthoserelevanttoaunittrip.
0 2.EQUIPMENT CLASSIFICATION ANDVENDORINTERFACE 2.1ReactorTriSystemComonentsFortherea'ctortripsystem,alistofcomponents isenclosed(Attachment 1).Includedinthislistarethesensorswhichmeasurethetripvariables andthecircuitsuptoandincluding thereactortripbreakers.
Thecomponents downstream ofthebreakers, suchastherodsthemselves, areexcluded.
Wedonotcontrolsafety-related components inthemannerindicated intheportionofthepositionstatedin2.1ofGenericLetter83-28thatstates,"...allcomponents whosefunctionisrequiredtotripthereactorareidentified assafetyrelatedondocuments, proceduresg'nd information handlingsystemsusedtocontrolsafety-related activities including maintenance, workorders,andpartsreplacement."
Rather,ourmethodofcontrolisdescribed below,asisthehistorical perspective ofhowitevolved.Attheconceptual designstage,AEPSCissuedaseriesofNuclearSafeguard'Design MemoswithintheCorporation toconvey,amongotherthings,theprinciples onwhichsafetyclassifications weretobemade.Attheconstruction stage,theQualityControlManualfortheD.C.CookPlant(Rev;3of1971)stated:"Thoseitemsvitaltosafeshutdownandisolation ofthereactor,orwhosefailuremightcauseorincreasetheseverityofalossofcoolantaccident, orresultinanuncontrolled releaseofexcessive amountsofradioactivity aredesignated classI.ClassIsystemsandcomponents areessential totheprotection ofthehealthandsafetyofthepublic.Consequently, theyaredesigned, fabricated,
'inspected anderectedtotheapplicable provisions ofrecognized codes,goodnuclearpracticeandtoqualitystandards thatreflecttheirimportance."
Thesedocuments constituted theoriginalbasisforequipment classification which,tosomeextent,isusedtoday.However,presentCorporate Procedures havemodifiedtheseclassifications todefinesafety-related components asfollows:"SafetyRelated(NItems)arethose':Whichareassociated withthea)safeshutdown(hot)ofthereactor,orb)isolation ofthereactor,orc)maintenance oftheintegrity oftheReactorCoolantSystemPressureBoundary.
OR2.Whosefailuremighta)causeorincreasetheseverity, ofadesignbasisaccidentasdescribed intheFSAR,orb)leadtoareleaseofradioactivity inexcessof10CFR100limits."
IhIJIP Electrical, civil,mechanical, andstructural itemswithknownexceptions, arelistedassafetyrelatediftheyare:1.SeismicclassI,2.Electrical classIE,3.Associated withtheEngineering SafetyFeaturesActuation System,4.Associated withtheReactorProtection System,or5.'afety-related forotherreasons,suchasportionsoftheFireProtection SystemandPost-TMIinstallations.
Components whichmettheaboverequirements (withknownexceptions) wereclassified assafetyrelated(N-Items) andenteredintoacomputerized listcalledtheN-List.Acomponent isthesmallestunitwhichisseparately identified inoriginalequipment procurement documentation.
Inotherwords,ifamotorcontrolcenterwasbought,asaunit,eachsub-assembly withinthatMCCwouldnotbeseparately enteredintheN-list.Structural itemssuchasconcrete, rebar,buildingsteel,etc.werecoveredbyalineentryperitem.Electrical itemssuchasrelays,switches,
- conduits, fittings, andtrayswerealsocoveredbyasinglelineentryperitem.TheN-listisoneofthedocuments utilizedtoidentifyequipment asbeingsafetyrelated.However,itisnotallinclusive andtherefore notthesolesourceofreference.
Whenspecificdeterminations mustbemade,otherdocuments suchastheFSAR>Technical Specifications, relatedcommunications totheNRC,flowdiagrams, isometrics, electrical oneline,andelementary diagramsarealsoconsulted.
ThecontroloftheN-list,including updateandmaintenance responsibilities, issetforthincorporate levelGeneralProcedures.
ZfanyonewithinAEPorthePlantisunsureoftheclassification ofacomponent, heisrequiredtocheckwiththeresponsible AEPSCCognizant
- Engineer, Underthepresentsystemofworkcontrol,aJobOrderispreparedforallrepairandmodification workperformed attheplant.Attachment 2isasampleJobOrder.DuringtheJobOrderpreparation process,thesafetyclassification (NorS)oftheequipment, aswellasprocedures requiredtoperformthework,areindicated ontheJob~Order form.Thepersonnel responsible fordesignating thesafetyclassification areexperienced andknowledgeable intheuseofthereference documents described above.Thesamereference documents, including purchaseordersandtheDCCSpecifications, areusedtoassurethatqualified replacement partsareutilizedwhenrequired.
Theprincipal supplyofcomponents whosefunctionisrequiredtotripthereactorwasthroughWestinghouse ElectricCorporation.
WehavereceivedfromWestinghouse alistofallchangesrecommended fortheequipment theyhavesuppliedfortheD.C.CookNuclearPlant.Verification byformalwrittendocumentation hasnotbeenobtainedon IId 4alltheseitems;however,Attachment 3liststhemodifications andtheirdisposition, including thereason(s) why.thechangewasnotincorporated.
Attachment 4describes thecontrolsthatapplytochangesaffecting theD.C.CookNuclearPlant.Webelievethattheseattachments demonstrate thatourprogramiseffective inaccomplishing safetyobjectives.
Toallowustosystematically trackvendordocumentation forthelifetimeoftheplant,.wearesettingupaVendorDocumentControlSystem.Attachment 5givesapreliminary description.
Wecurrently anticipate havingaprogramcompleted andinplace.bytheendof1985.Basedontheabove,itisourbeliefthatwecurrently haveaneffective programtoassurethatallcomponents whosefunctionisrequiredtotripthereactoraretreatedinamannerwhichisnotinimicaltopublichealthandsafetyand,althoughnotthesameastheNRCstatedposition, willaccomplish whatwebelievetobetheintendedsafetyobjective oftheNRC.Wehavereviewedthetripcomponents listtomakesurethat,exceptasnotedonAttachment 1,eachitemisontheN-listand,thus,underthecontrolscitedabove.Wecannotatthistimesubmitastatement confirming thattheyconformtothepositionregarding equipment classification because,asdescribed above,wehaveadifferent programinthisarea.Development oftheprogramcitedinEtem2.1ofGenericLetter83-28wouldconstitute amajorundertaking andwould,inalllikelihood, take'onsiderable time.Zfforanyreason,theNRCshouldfindourresponsein<hisareatobeunacceptable, wewouldliketomeetwithyourstafftodiscussalternative approaches.
I 2.2EquimentClassification andVendorInterface (ProramsforallSafet-RelatedComonents)ThissubjectisbeingreviewedindepthwithinAEPSCandtheD.C.CookNuclearPlant.Inviewoftheconsiderable scopeoftheprogramsinvolved, theamountofdetailedinformation necessary, andtheinput fromINPOonvendorinterface, weanticipate thatwewillneeduntilMarch30,1984torespondtothissection.
1'PI 3.POSTMAINTENANCE TESTINGReactorTripSystemComonentsPost-Maintenance TestingWehavereviewedourtestandmaintenance procedures andTechnical Specifications andhavedetermined thatpost-maintenance operability testingofreactortripsystemcomponents isrequiredtobeconducted priortoreturning thesystemorcomponents toservice.Thetestingdemonstrates thattheequipment iscapableofperforming itsintendedsafetyfunction.
Itshouldbenoted-thattherearecomponents suchascontrolswitches, inverters, batteries, andcablepenetrations thatareverifiedoperableaspartofasystemtestorbyverifying outputparameters.
Post-maintenance operability verification requirements forworknotcoveredbyaspecificprocedure isreviewedandestablished aspartofthejoborderreviewprocess,theplantdesignchangeprocedure, andtheclearance permitsystem.Plantinstructions governing maintenance workanddesignchangesarepresently undergoing reviewaspartofourRegulatory Performance Improvement Program.Thisreviewincludesspecificinstructions toaddressbothpost-maintenance testinganddesignchangeinstallation operability testing.Recommended TestsWehavereceivedfromWestinghouse theirTechnical BulletinNSD-TB-83-05 whichlistsalltheirTechnical Bulletins andDataLetterssenttomembersoftheWestinghouse Owner'sGroupasofJune20,1983.Wehavereviewedallthesebulletins andforthosethatpertaintothetripsystem,wehaveassuredourselves thattheinformation wasconveyedtocognizant engineers atAEPSCandtherelevantDepartment atthePlant.Changesintestingandmaintenance procedures promptedbythesebulletins havebeeninitiated.
ForvendorsotherthanWestinghouse, wehavestartedtosendoutlettersrequesting alistoftheirdocuments thatpertaintoreactortripcomponents sothatwemayverifytheirincorporation.
Conditional toourreceiving theinformation fromourvendorsonatimelybasis,wewillattempttoverifythedisposition ofallofthesemodification noticespriortoMarch30,1984.Excessive Technical Specification MandatedTestingIWeareawareoftheNRCTaskForceonPlantTechnical Specifications Surveillance Requirements anditseffortstoenhancesafetyby.seekingoutoptimumpost.-maintenance testingfrequencies.
AEPSCisamemberoftheWestinghouse Owner'sGroup(WOG)whichhasanactivesubcommittee onTechnical Specifications.
I OnSeptember 16,Mr.J.J.Sheppard, thechairmanofWOG,wrotetoMr.J.Sniezek,Directorofthe.DEDROGRstaff,outlining theOwner'sGrouppositiononthisissue.Wesupportthepositionandphilosophy contained intheletter,particularly thecommentontoofrequentstartuptestingofdiesels.Wedonotintendatthistimetoseparately submit:anapplication forreducedtestingwithsupporting justification todemonstrate thatsafetyisdegradedratherthanenhanced.
0 3.2AllotherSafet-RelatedCpmonentsDuetothelargevolumeofactivityassociated withthisresponse, wearecurrently scheduling ourresponseinthismattertobeissuedonMarch30,1984foritems3.2.1and3.2.2.Foritem3.2.3,ourresponseisthesameasthatpresented underitem3.1.3. 4.REACTORTRIPSYSTEMRELIABILITY IMPROVEMENTS Vendor-Related Modifications AppendixAofWestinghouse Technical BulletinNSD-TB-83-05, datedJune20,1983,hasbeenreviewedbyAEPSCCognizant Engineers.
Exceptforthosebulletins listedinAttachment 6,allthosechangesthatrelatetoourplanthavebeenorarebeingimplemented.
Plantpersonnel areawareofthecontentsofbulletins listedinAttachment 6.AreviewofthePlantprocedures isunderwaytoensurethatnecessary updatesaremadel'hemodifications recommended inNCD-Elec-18 relatetocertainproblemsidentified inDB-50reactortripbreakerspriortodeliverytotheD.C.CookPlant.Corrections weremadebythemanufacturer.
TheWestinghouse Owner'sGroupsentusa.letter(83-242ofSeptember 15,1983)askingforvisualconfirmation thatwehadapost-1972 UVTAUnit.ThiswasdoneattheCookPlant.NoticeNCD-Elec-18 doesnotapplytoourplant.WehaveverballybeeninformedbyWestinghouse thatadditional Bulletins (suchas83-02Rev.1)willbesenttousintheverynearfuture.Whenwereceivethemwewillactonthem.
4.2Preventative Maintenance andSurveillance ProgramforReactor4.2.1PeriodicMaintenance Thecurrentmaintenance program(exceptforfrequency) forthereactortripbreakersisincompliance withtheWestinghouse recommendations contained inWestinghouse Technical Bulletin83-02.Priortotheissuanceofthisbulletin, theprocedure wasincompliance withtherecommendations ofBulletin74-02.Thecircuitbreakersareinspected, cleaned,andlubricated duringeachrefueling outage.Criticalclearances areverifiedtobewithintolerance byuseofgo/no-gogauges.Instructions foradjustments areincludedinthemaintenance procedure.
4.2.2Parameter TrendingTheperformance oftheundervoltage tripdevicewillbemonitored duringscheduled inspections byreducingtheappliedvoltagetotheundervoltage tripcoilandrecording thetripvoltage.Atleastthreevaluesforeachcircuitbreakerwillbeobtained.
Futurevalueswillbecomparedforindividual circuitbreakerstomonitoranychanges.Comparisons willalsobemadebetweencircuitbreakers.
Criteriaforevaluating changesarebeingdeveloped andareexpectedtobeinplacebytheendof1984.
4.2.3and4.2.4LifecleTestingandperiodicRelacementLifecycletestingof.theshunttripattachment (STA)andtheundervoltage tripattachment (UVTA)ofthereactortripswitchgear isbeingconducted byWestinghouse fortheWestinghouse Owner'sGroup.Thisprogramisaimedtowardestablishing theservicelifeofthesedevicesandsubstantiating periodictestrequirements withpropermaintenance.
1TheUVTAtestingfortheDB-50breakersiscompleteandweareexpecting areportbytheendofNovember1983.Thebalanceoftheprogramisscheduled forcompletion inthesecondquarterof1984.Anychangestopreventative andcorrective maintenance orreplacement intervals indicated bytheresultsofthetestswillbeconsidered forincorporation intoourexistingprocedures.
0 4.3.Automatic Actuation oftheShuntTriAttachment forWestinhouseandBSWPlantsWeintendtomodifythereactortripsystemsothatincaseofanautomatic trip,boththeShuntTripAttachment (STA)andUnderVoltageTripAttachment (UVTA)willcause<hereactortripbreakerstoopen.TheWestinghouse Owner'sGroupaskedWestinghouse todesignthisautomatic actuation feature.Adetailedgenericdesignpackagewasdeveloped andtr'ansmitted toHr.EisenhutbyJ.J.Sheppard(Chairman, WOG)byletteronJune14,1983.TheNRCissuedaSafetyEvaluation ReportonthegenericdesignonAugust10,1983(letterD.EisenhuttoJ~J.Sheppard).
Severalquestions wereraisedandadditional information requested inthatReport.TheReportconcluded thatthegenericdesignwasacceptable butpointedouttheplant-specific information required.
WewillconsidertheSTAtobeasafety-related functionandstipulate thatthecircuitry usedtoimplement itmustbeclassIE.Westinghouse
'isproceeding toqualifytheSTAtoIEE323-74and344-75criteriaandtoconductseismictestsandissueacompletetestreport.Thepresentschedulecallsforcompletion oftheirworkinsevenmonths.Onreceiving afinalgenericdesignfromWestinghouse, wewillbestartingaplant-specific design.Adesignpackagewillbesubmitted totheNRCforsafetyevaluation.
Weareunabletogiveyouanimplementation schedulebeforereceiptof-thecompleteWestinghouse designpackageandreport.
II 4~4~Improvements inMaintenance andTestProcedures forBGWPlantsThisSectiondoesnotapplytotheD.C.CookPlant.
4.5SstemFunctional Testing4.5.1..STAandUVTATestingThereactortripbreakersarecurrently testedon-line,byoperation oftheundervoltage tripdevice.Thepresentarrangement offourcircuitbreakers, twotripandtwobypass,permitson-linetestingofthebreakers.
Wecuriently testtheUVTApriortoeverystart-upandonceeverythreemonthsduringunitoperation.
Theshunttripisindependently testedpriortoeachstart-up.
Nofailures.havebeenencountered.
4.5.2.Oncethemodification toenable'utomatic actuation oftheshunttripattachment ismade,wewilltestboththeUVTAand-theSTAwhiletheunitisinoperation.
On-lineTestingSinceweperfoxmon-linetesting,thissectiondoesnotapply,toourplant.4.$.3.Frequency ofOn-lineTestingOurpositionisasfollows:ThereactortripcircuitbreakersattheD.C.CookPlantareinstalled inacleananddxylocationandarenotsubjecttoanydeleterious environmental influences.
Thepresentmaintenance programrequiresthatthecircuitbreakersbeservicedateveryrefueling outage.Atthistimethemechanical featuresofthecircuitbreakersareinspected andadjustedasnecessary tomaintainthecriticalclearances determined bythemanufacturer tobenecessary forreliableoperation.
Thecircuitbreakeranditscompartment arecleanedandlubrication isappliedasrecommended bythemanufacturer.
Themaincontactresistance is'erified tobeacceptable bytest.Thecircuit,breakersaretheninstalled inthemetalcladenclosures.
Priortoreturning thecircuitbreakertoservice,anelectrical functional testisperformed whichteststheelectrical closing,electrical shunttripandtheundervoltage trip.Zncompliance withtheTechnical Specifications, theundervoltage tripofeachcircuitbreakerhasbeentestedonlineatthree-month intervals.
Therehavebeennofailuresofthereactortripcircuitbreakerstotripduringtestsorinactualopexation.
Thishistoryofexcellent performance hasbeenmaintained forover7yearsforoneunitand4yearsfortheother.Thepresent r' surveillance and'maintenance programhasbeenadequate, resulting innofailures.
Thepresent'maintenance schedulepermitsinspections andadjustments tothecircuitbreakersatintervals whicharemorefrequentthannecessary, considering thecleanenvironment andlightelectrica'1'ervice requiredofthecircuitbreakers.
Thetestingatthree-month intervals hasprovidedthenecessary exercisetoensurefreedomofmotionofthecircuitbreakersanditsattachments whentheyarecalledontooperatetoperformtheirsafetyfunction.
Assumingamaximumtestintervalofonehourforeachon-linesurveillance testforeachcircuitbreaker,thereactorprotection systemisdependent ononesafetytrainfortrippingfortwohourseverythreemonths.Increased on-linetestingfrequency willresultingreatertimedependency ononetrainfortrippingwithoutincreasing theassurance thatthereliability ofthecircuitbreakershasbeenimproved.
TheWestinghouse Owner'sGroupiscarryingouttestsonthesebreakers.
Weexpecttoreceivetheir.resultsinFebruary1984.Ifthereareanychangeswefeelweneedtomakeasaresultofthetests,wewillcommunicate toyoubyMarch30,1984.
0I)1J ATTACHMENT 1toAEP:NRC:0838A REACTORTRIPSYSTEMCOMPONENTS INSTRUMENTS SteamGenerator LevelSteamPressurePressurizer PressureContainment PressureBLP-110120130140ill121131141112122132142MPP-210220230240211221231241212222232242PPP-300301302NPP-1511'52153NPS-1'53ReactorCoolantTemeratureNTP-110Turbine1stStagePressure120MPC-253*130254*140TurbineControlFluidPressure111LPS-90*1219]*13192*141MainFeedWater FlowReactorCoolantSystem'10 FFC-210220230240211221231241MainSteamMFC-110120130140ill121'131141FlowFlowNFP-210220230240211221231241212222232242220230240211221231241NuclearFluxMonitorsN-3132353641Pressurizer Level42NLP-15143152441'53CONTROLSWITCHES101-RTA101-RTB6-SIA16-SIA26-SIB16-SIB25-PSIA5-PSIB5-SSIA.5-SSIBRELAYS96-DDF96-1AUF96-1BUF96-1CUF96-lDUF96X-AUFB96X-BUFB96X-AUFA96X-BUFA96X-CUFB96X-DUFB96X-CUFA96X-CUFB RELAYSATTACHMENT 1gCont'd)MISCELLANEOUS 27-AUV27-BUV27MUV27-DUV27-lAUV27-1BUV27-1CUV27-DUV62-27X-AUVB 62-27X-BUVB 62-27X-AUVA 62-27X-BUVA 62-27X-CUVB 62-27X-DUVB 62-27X"CUVA 62-27X-DUVA 96-AUF96-BUF96-CUF4KV-BUSlAP.T.4KVBUS1BP.T.4KVBUS1CP.T.4KVBUS1DP-T.ACB52-1B9AUX.ACB52-1C2AUX.ACB52<<1D9AUX.ACB52-lA4AUX.33-SVS-133-SVS-233-SVS-333-SVS"4SW.*SW.*SW.*SW.**NonN-gradecomponent Rationale fortheuseofnonN-gradecomponents intheReactorTripSystem:SomedeviceswhichprovidecontactclosurestotheReactorProtection Systemarenotincludedonthe"N"list.These,devicesarelocatedinareaswhichdonotmeettherequirements forsafety-grade structures suchastheturbinebuildingorareconnected toequipment whichhasnoothersafetyfunctionsuchasthereactorcoolantpumpcircuitbreakersandtheirsourceelectrical busses.Thetripfunctions providedbythesecontactsareusedtodevelopanticipatory trips.Thebuspotential transformers usedastransducers forthefourreactorcoolantpumpmotorsourceelectrical bussesareconnected tonon-safety gradebusses.Thepotential transformers cannotbesafetygradeorclassIEiftheirenclosure isnotalsoclassIE.Thesepotential transformers providethevoltagetotheundervoltage andunderfrequency relayswhichprovideananticipatory tripofthereactoronlowreactorcoolantflow.Thesebuspotential transformers areidentified as"4kvBUSlAPT"forthelAbus.Similardesignations areusedforbusses1B,1C,lD<2A~2B>2C,and2D.Thereactorcoolantpumpcircuitbreakerpositionswitchesarelocatedincircuitbreakersinnon-safety busses.Thesecircuitbreakerpositionswitchesprovideaninputtothe:logic todevelopananticipatory tripofthereactorontripofreactorcoolantpumps.Theseswit'ches areidentified as"ACB-52-1B9 auxsw."forcircuitbreaker1B9.Similaridentification isusedforcircuitbreakers1C2,1D9,lA4,2B9,2C2,2D9,and2A4.
I"I11' ATTACHMENT 1(Cont'd)Twosetsofdevicesonthemainturbineprovideinputcontactstothereactorprotection logicsystem.Theturbinehydx'aulic tripsystempressuxeissensedbypressureswitcheslocatedinthe<urbinefzontstandard.
Alossofpressureindicates thatthetuxbinehasbeentripped.Thesedevicesareidentified asLPS-90,LPS-91,andLPS-92.Twosetsoflimitswitchesoneachturbinemainstopvalvealsopz'ovideinputcontactstothereactorprotection logicsystemtoindicateclosureofthemainstopvalves.Closureofallfourmainstopvalvesisaredundant indication ofturbinetrip.Thetripsystempressureswitchesandthemainstopvalvelimitswitchesarelocatedonthemainturbinewhichisnotasafety-related device.Thedevicesdevelopanticipatory trips.Theseswitchesareidentified as"33-SVS-1",
"33-SVS-2",
"33-SVS-4."
Twopressuretransducers, MPC-253andMPC-254,arelocatedadjacenttothemainturbineandareusedtosensetheturbinefizststagepressureasameasureofturbineload.Thesetransducers arenotlistedonthe"N"listbecause<heyareturbine-mounted devices.Exclusion ofalloftheaboveitemsfromtheN-listdoesnotconstitute anunreviewed safetyquestionasdefinedin10CPR50.59,nordoesitcreateasubstantial hazard.tothehealthandsafetyofthepublic.
'II~INI\ ATTACHMENT 1(Cont'd)MISCELLANEOUS ReactorTripSwitchgear SolidStateProtection System-Input,Output,LogicCabinetsReactorProtection Channel1,Cabinets1-4II2I5-8II3I'>>11II4"1213ReactorProtection Aux<abinetsAuxCabinetsRPSX-AandRPSX-BControlPanel-FLXIIPR2II-SISII-SGIISARCable-Item53064II3073II3074II-3075II3076II3077II3111If3112tl3119tl3120II3121II3122II3123I13124II3125II0871II0872Electrical Instrument Penetration EP-08tlEP-10IIEP-llElectrical Instrument andControlPenetration EP-12ZnverterandDistribution CabinetCRZDI.IICRIDIZIICRZDZIIIICRIDIV250VDCPlantBatteries
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spp'ee""".m'RzLLo'rMrp r0~NL~'!@..'roppAspA',Given>to N$7RPS'>Co'nditioqARep'ort~~sDa'ta Histci'"~,'>'gq~P3++3%JN'&ATE"'>"'>Pm&WMQWW'lg~yf' C~(Y'II
-30>>ATTACHMENT 3toAEP:NRC:0838A LISTANDDISPOSITION OFWESTINGHOUSE RECOMMENDED CHANGESAFFECTING REACTORTRIPSYSTEMSBulletin75-17122975.Disposition Looseterminalaonnections forpowersupplyinverters.
ThisappliedtoWestinghouse Inverters anddoesnotapplytoD.C.Cookplantsincesolidstateinverters areused.77-10072177.ARrelayswithlatchattachment.
Allrelayswereinspected andthosehavingtheaffecteddatecodeswerepurgedfromtheinstalled systemarfromstock.Nofurtheractionisrequiredatthistime.79-02041779.Overcurrent tripdevicesonDBcircuitbreakers.
Notapplicable tothesafetysystemsofD.C.Cookplant.Noactionrequired.
82-03-Rl121482.ARrelayswithARMLAattachments.
Wehavetherelaysandhavequalified themseismically.
Nofurtheractionisrequiredatthis.time.83-02032483.Reactortripbreakermaintenance.
Recommended actionhasbeenincorporated inplantmaintenance procedure forreactortripcircuitbreakers.
83-03032483.Reactortripcircuitbreakertesting.Testprocedures havealreadyincorporated separatetestforundervoltage andshunt,tripdevices.
ICl'I'8 ATTACHMENT 3(Cont'd)NSZDLetterDissition63-02061063.Tutorialinformation onnoisecouplingintoinstrument circuits.
Nospecificactionidentified.
Noactionrequiredatthistime.68-14051568.Tutorialinformation onlead/laginstrument systems.Nospecificactionidentified.
Noaction;requiredatthistime.68-25073168.Misuseofvitalinstrument bus.Generalinformation andprecautions.
Nospecificactionidentified.
Noactionrequiredatthistime.68-26073168.Misuseofvitalinstrument bus.Generalinformation andprecautions.
Nospecificactionidentified.
Noactionrequiredatthistime.68-26080768.Unauthorized fieldmodifications.
Appliedtoturnkeyinstallations.
Doesnotapply.toD.C.CookPlant.Nofurtheractionrequired.
70-18091870.AmphenolTriaxCabledefects.NoAmphenoltriaxcableisusedatD.C.CookPlant.Nofurtheractionisrequired.
72-80080272.Znvertertests.DoesnotapplytoD.C.CookPlantsinceWestinghouse inverters arenotused.
~lp1 ATTACHMENT 3(Cont'd)INSTRUMENTATION 6CONTROLTechnical DataLetterNo.Disposition 69-4UnitsReferenced inletter(M/63SandM/635DR)arenotatourfacility.
Ourunitsare63R,63U,63U-Dor63U-E,F.70-21DropTimeTestProcedure 12THP4030STP.387 isinaccordance withletter.71-17SULetterimpactsinitialstartupandwouldnotaffectoperating plant.Technical BulletinDissition73-6TheCoolantflowprocedures THP6030IMP.099 (U<<l)andTHP6030IMP.
199(U-2)areproperlyscaledforthebistableinputs.Secondary steamflowhasasquarerootextractor beforethebistableinput.73-19Connections involvetheoperating coilandwouldnothamperareactortrip.73-20Plantpresently exercises thesepotsduringcalibration.
75-6ReviewofWestinghouse-supplied amplifiers indicates nonearethesuspectmodels.Ref.AEP/AMPWNESInstrumentation manualindicates allamplifiers areFoxboroModel66BC-O.77-11Plantprocedures THP4030STP.045 (U-1)andTHP4030STP.145 (U-2)utilizetheprocedure reference inthisTechBulletin.
78-281-12Wouldnotinhibitatrip.NoFoxboro92B'sarebeingusedatourplant.
IIJ ATTACHMENT 34Cont'd)DataLetterDisposition 80-03022980.AmphenolInstrument connectors.
Rexoliteinsulated connectors.
Wewillinitiateanewattempt'to obtainconnectors withtherecommended insulation.
Attemptstoobtaintheseconnectors fromAmphenolwereunsuccessful inthepast.81-02062481.instrument invertertransformer redesign.
DoesnotapplytoD.C.CookPlantsinceWestinghouse inverters arenotused.82-07041382-instrument inverters.
AppliestoWestinghouse inverters.
Notapplicable tosolidstateinverters.
ar ATTACHMENT 3(Cont'd)Theremaining itemslistedbelowweredeteminednottoimpacttheReactorTripFunction:
Technical Bulletins:
73-173-773-1573-1674-474-874-1474>>14SupplA75-175-380-280-380-480>>780-1080-1175-575-5SupplA75-07-Rl75-875-075-1275-1375-14-Rl75-1575-1881-181-281-381-4-Rl81-781-876-176-376-476-676-776-876-976-11-Rl76-13,76-1481-081-1081-1382-182-282-476-1577-377-477-577-677-777-877-977-1277-1482-582-682-783-183-478-1-Rl78-378-4-Rl79-379-479-679-779-879-980-1NSIDDataLetters59-361-362-463-163-463-564-264-467-468-168-268-468-568-7-Rl68-8-Rl68-1168-1268-1468-1578-478-578-678-778-878-978-10-Rl78-1178-1279-379-579-679-780-180-2-Rl68-1968-2768-2968-3168-32-R268-3368-3668>>3779-369-769-969-1069-1169-12-R369-1469-15-R269-1669-1969-2080-5-Rl80-680-980-1081-182-182-282-382-4-Rl82-582-682-882-982-1069-21-Rl69-2369-2469-2970-270-370-6-R370-870-970-1270-1570-1670-1770-2070-2270-2571-171-3SU82-1282-1371-471-85U71-9SU71-1271-1471-1571-1671-2071-21-Rl72-172-3SU72-472-5R172-6SU72-772-9SU72-12SU73-3.SU73-373-974-174-474-775-275-675-776-276-376-577-2-Rl77-477-677-778-178-278-3 r44
.~-35-ATTACHMENT 4toAEP:NRC:0838A CONTROLOFDESIGNCHANGESDONALDCCOOKNUCLEARPLANTChangestosafety-related equipment, systems,and/orstructures (engineering designchanges)arecontrolled byaCorporate levelprocedure.
Thisprocedure issupplemented bylowertierorganizational unitspecificprocedures ifnecessary.
Thevehicle-forinitiating, reviewing, approving, designing, and-implementing anengineering designistheRequestForChange(RFC).RFCsmaybeinitiated eitherbytheCookPlantstafforAEPSC.RFCs,regardless oflocationoforigin,areassignedtoaLeadEngineerinthecognizant AEPSCengineering ox'esignsection.TheLeadEngineerisresponsible forthedevelopment oftheproposedchangeandthe-coordination ofinterdisciplinary review,scoping,andcosting.Once-theconceptual designforanRFChasbeencompleted, theRFC-isreviewedandapprovedbytheLeadEngineer's supervisor, androutedtotheAEPSCNuclearSafetyaLicensing Section(NSaL)forreview.NSGLreviewstheRFCforsafetyimplications, highlights anysafetyissuesandsafety-related
- features, andassuresthattheproposedchangewillnotcreateasignificant hazardtothehealthandsafetyofthepublicanddoesnotconstitute anunreviewed safetyquestionasdefinedin10<FR50.59.Uponcompletion ofNSaL'sreview,theRFCisforwarded totheCookPlant,PlantNuclearSafetyReviewCommittee (PNSRC).ThePNSRCreviewstheRFCforsafetyimplications, desirability, necessity, andalsoconsiders theopex'ability andmaintainability ofthechange(fromasafetystandpoint) duringbothinstallation andsubsequent service.OncethePNSRCacceptstheRFC,itisroutedtothePlantManagerforhisreviewandacceptance.
ThePlantManagerthenroutestheRFCbacktoAEPSCforsubmittal totheChangeControlBoard(CCB).TheCCBreviewstheRFCtoassurethatproperconsideration hasbeengiventotheimpactthattheproposedchangemayhaveonplantsafety,testprograms, procedures, costs,schedules, andcurrentplantstatus.TheCCBdetermines thattheproposedchangegivesproperconsideration togoodengineering, design,construction, andoperating practices fornuclearplants,andthattheproposedchangemeetstherequirements ofapplicable codes,standards, andguidelines.
AfterCCBapproval, acopyoftheRFCisforwarded totheAEPSCNuclearSafetyDesignReviewCommittee foroff-lineindependent review.TheNSDRCismandatedbytheCookPlantTechnical Specifications toindependently reviewthesafetyevaluation performed byNSaLforchangestoequipment orsystemscompleted undertheprovision of10CFR,50.59 toverifythatthechangedidnotconstitute anunreviewed safetyquestion.
0~~~(6 TheoriginalRFCguponCCBapprovalg isreturned'to'theLeadEngineerforinitiation ofthe"interactive" engineering designprocess.Thisresultsinthegeneration ofthedetaileddesignrequiredtoimplement thechange.Inparallelwiththisprocess,engineering documents impactedbythechangearerevised.Thisactivityiscompleted whenalldesigndocuments necessary toimplement thechangehavebeenissued.Priortoonsiteimplementation ofachange,achecklist (RFCInstallation Authorization) mustbecompleted andsubmitted forapprovalbyplantmanagement.
Thislistidentifies:
flanyprecautions andlimitations, theindividual responsible forcoordinating theimplementation ofthechange,thesupervisor responsible fortheimplementation, anytestingrequiredbytypeandscope,anyinstructions and/orprocedures requiring
- revision, andwhowillperformtheactualphysicalimplementation.
Uponcompletion ofthechange(s),
adetailedRFCFinalSummaryReportmustbepreparedandanRFCReleaseandReviewForminitiated.
TheRFCFinalSummaryReportisusedtoensurethatallitemsidentified ontheRFCInstallation Authorization havebeencompleted andthedrawingsusedduringtheoperation oftheplanthavebeenrevisedtoreflectthechange.TheRFCReleaseandReviewFormisusedtoprocesstheRFCtocloseoutandtosecuresignatures necessary todeclarethechangeoperableandavailable forunrestricted use.Thisdescription highlights thechangecontrolprocess.Theattachedflowchart providesfurtherdetails.
II0cCyIU
tieC'~II ATTACHMENT 5toAEP:NRC:0838A VENDORDOCUMENTCONTROL'SYSTEM(VDCS)Weareintheprocessofsettingupacomputerized VendorDocument<ontrolSystem.Alltechnical information receivedfortheD.C.CookNuclearPlantwillbeprocessed throughthissystemregardless ofwhether-thevendorsenttheinformation totheplantortotheCorporate office.Itiscurrently envisioned thattheVDCSwilloperateinthefollowing manner:Acentralgroupwillprovidealog-inprocedure whichwillallowforsystematic storageand-retrieval ofdocuments byselectedfields.AnydocumentthatdoesnotpertaintoCookwillterminate here.Applicable documents willbesenttotheCognizant Engineerfor'isposition.
Wheremorethanonediscipline isinvolved, aresponsecoordinator willbenamedwiththeresponsibility ofensuringthatproperactionistakenandthecomputerrecordsupdated.Transmittals between,theCentralgroup,theEngineering Divisions oftheAEPServiceCorporation, andthePlantwillbetrackedbytravelerforms.Anyplantordesignchangeinitiated byavendordocumentwillbereferenced byitsPlantModification (PM)orRequestForChange(RFC)number.ExistingPlantandCorporate Procedures takeoverforthecontrolofchanges.Periodically, allvendorsontheVendorDocumentControlSystemwillbeformallycontacted andrequested tofurnishalistofalltechnical documents senttoAEPortheCookPlant.Thislistwillbecompared'o thecomputerlist.Anydocuments missingfromtheVDCSwillbeobtainedfromthevendorandprocessed inthenormalmanner.TheCorporate Procedure isbeingdraftedandthecentralgroupandcomputersupportpersonnel havebeenidentified.
Theimplementation detailshaveyettobeworkedout.INPOisworkingontheproblemfromthe'generic standpoint ofwhatdocuments aretobecontrolled andhowtogarnervendorsupport.Sincethisresponseisinpartdependent oninputfromanoutsideorganization, i.e.,INPO,itisnotyetpossibletodevelopanimplementation schedule.
Weanticipate thatwewillbeabletoprovidethatimplementation scheduleonMarch30,1984.
'0tt'4'El>rN't ATTACHMENT 6TOAEP:NRC:0838A REACTORTRIPSYSTEMRELIABILITY WESTINGHOUSE BULLETINS BEINGIMPLEMENTED'ELEVANT PLANTPROCEDURES BEINGREVIEWEDFORUPDATENumber79-0480-0380-580-0780-873-2074-377-380>>880-6BulletinorDataLetterDBDBBDDDDescription SolidStateProtection SystemP-4Permissive TestNuclearInstrumentation Connectors-AmphenolDelta-Flux Instrumentation Calibration FoxboroTransmitter JunctionBoxSourceRangeDetectorMulti-Turn Potentiometers FoxboroTransmitters-Calibration SolidStateProtection System-ExtenderBoardsBartonTransmitter Potentiometer OxideDepositBeingaddressed byRequestForChange(RFC)12-2512 VPcSq