ML17250A847

TMI Action Plan (NUREG-0737) Documentation.

ML17250A847
Person / Time
Site:	Ginna
Issue date:	12/30/1980
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17250A846	List: ML17250A845 ML17250A847
References
RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8101060468
Download: ML17250A847 (85)

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ATTACHMENT ARochester GasandElectricCorporation TMIActionPlan(NUREG0737)Documentation KI-:IILNIIII7 MI',IlHfIKMWDecember30,1980 Cik,1y,,

1.A.1.1ShiftTechnical Advisor~~Adescrxptxon ofouroriginalSTAprogramwasoutlinedinaletter,datedOctober17,1979,fromL.D.White,Jr.toMr.DennisZiemann,withadditional information

.providedinaletterdatedDecember28,1979,fromMr.WhitetoMr.Ziemann.InresponsetotheNRC'sletterdatedJuly7,1980,fromMr.DennisCrutchfield weprovidedadditional clarification ofouroriginalSTAprogramandadescription ofournewSTAprograminaletterdatedAugust5,1980fromL.D.White,Jr.toMr.Crutchfield.

OuroriginalSTAprogramutilizedlicensedoperators andincludedtheirparticipation incollege-level engineering coursestoprovidethemeventually withanengineering degree.AttherequestoftheNRCRG&Emodifiedtheoriginalprogramandassignedeitherdegreedengineers orSRO'sasSTA,andassigneddegreedengineers toperformtheOperational Assessment function.

WebeganstaffingtheOperational Assessment, Groupinthesummerof1980.OurSTAtrainingandrequalification programisdescribed byaGinnaStationAdministrative Procedure, andconsistsofvariousphasesasdescribed below.PresentLevelofTraininInitialtrainingtomeettherequirements listedinHaroldDenton'sletterdatedOctober30,1979toAllOperating NuclearPowerPlantshasbeencompleted.

Thistrainingincludedafourweekclassroom trainingandtwodaysimulator trainingprogrampresented byourNSSSsupplieraslistedbelow.Title:Chemistry/Basic Theory,Objectives andControlObjective:

1.Discusstheconcernsthatrequirechemistry control2.DiscusstheRCS/Steamside Chemistry limitations andbasis3.Discussthetechniques formain-tainingchemistry limits4.DiscusstypicalRCS/Steamside chemistry problemsandtheassociated corrective actions5.Discusstheeffectsofchemistry upsetsonplantoperations 6.Discusschemistry indications forvariousaccidents 6

2TopicSummary:1.Functional Requirements 2.Chemistry ControlAreas3.Specifications, Limits,andBasis4.Mechanisms forControl5.ProblemsinControl6.Chemistry TroubleShootingTitle:Metalurgy/Basic FractureMechanics Objective:

Reviewtheoryoftheplantlimitations andoperational considerations basedonNSSSmetalurgical restrictions.

TopicSummary:1.Introduction 2.FractureCriteria3.StressAnalysisofthePWRVessel4.CrackTipStressIntensity FactorAnalysis-MethodsofDetermining StressIntensity FactorK5.MaterialProperties 6.Non-Destructive Examination 7.CodesandStandards 8.FractureMechanics Applications intheNSSS9.ReviewofPastandCurrentR&D10.PlantSpecificLimitsReviewTitle:Thermodynamics, HeatTransfer, andFluidFlowandtheirPWRApplications Objective:

Giveworkingknowledge oftheabovetopicsattheoperation level.TopicSummary:2.Basicproperties offluidsandmatter(energyrelationships)

FluidDynamics(addresses naturalcirculation)

Thermodynamics andHeatTransfer(boiling) includesmonitoring oftemperatures, flow,pressureparameters NormalPlantOperations (asperheatgeneration)

-peakingfactorsasafunctionofprimaryandsecondary system,management ofnormalreactorheat,anddecayheattransferlimits(boiloffisdiscussed)

L'lt1*,,~kO 35.Limitingphenomena a.burnout-DNBb.flowinstability c.sonicvelocity-chokedflowd.pumprunoute.thermaltransients

-metalfatiguef.foulingg.flashing-heatstoredinmetalh.blowdowntocontainment i.fueltemperature

-DNBj.steambindingk.Zirc-water reaction6.AccidentTreatment

-heatsinksandpressure/temperature limitsa.lossofRCPb.smallLOCAc.decayheatTitle:NuclearCharacteristics/Review Objective:

Comprehensive reviewofthereactivity effects,magnitudes, anddirection ofeachcorereactivity coefficient andthekineticeffectsofeachforatypicalPWRcycle,changesfromcoldtohot,androdbankposition.

TopicSummary:1.Subcritical Multiplication 2.Sixfactorformula3.Coefficients 4.Defects5.Inhourequations 6.Practical Application

-(measurements) a.Moderator Coefficient b.PowerCoefficient c.RodWorth7.NeutronMechanics Title:NuclearPeakingFactorsObjective:

Comprehensive reviewofFandF>Hincluding thebasis,limitations, andmeasurements ofeach.TopicSummary:2.3.5.Establish limitations ofeacha.Fuelb.Clad(includes Zr/H20reaction) c.FlowMeasurements ofFandF><Protection availa8le DElimitations Technical Specifications 6

Title:NSSSInstrumentation; Basis,Limitations andAlternatives Objective:

DefineNSSSinstrumentation basis,limitations andalternate sourcesofinformation.

TopicSummary:1.Requirements andBasisforParameter Monitoring 2.Instrumentation Limitations 3.Alternate SourcesofInformation 4.Believability ofInformation 5.BehaviorDuringAbnormalConditions 6.AdverseEnvironmental EffectsTitle:NSSSOperating Experience andSystemAssessment Objective:

Enhancetheoperator's abilitytoestablish systempriorities usingcontrolroominstrumentation.

TopicSummary:1.Establish conceptual approachtooperations

-(normal,abnormal, andemergency) 2.SelectedIndustryLER's3.Systemsproblemsarepresented;.

classmustchooseandsetthepriorities andcourseofaction.Title:NormalPlantTransient Assessment Objective:

Enhancetheoverallknowledge levelofnormalplanttransients, including theinstrumentation

required, themagnitude anddirection ofeach.TopicSummary:2.3.DevelopaBasicOperating Planta.Instrumentation Requiredb.Protection Requiredc.HeatBalanceIntroduction ofonestandardtransient assessment graph(Uses,controlroominstrumentation ranges)StepLoadChangesMajorLoadRejection ReviewofT-TrefMismatch/Re60ns LkP4 9.Title:5.MainGenerator TripCalculation oftheResultant avgInstrument FailureAssessment Objective:

Foranyselectedinstrument failure,predictthemagnitude anddirection ofeachmajorNSSSparameter andgraph.thefunctionassumingnooperatoraction.TopicSummary:1.Classestimates response(nooperatoraction)2.Thefollowing failureswereselectedformaximumimpact:a.TFailsHighatBOLb.NSgPowerRangeFailsHighatBOL3.TurbineImpulseChannelFailsLow4.Pressurizer PressureControlChannelFailsHigh5.Pressurizer LevelControlChannelFailsHigh/LowEachcalculation isconcluded wheneithertheplanthastrippedorastablereactivity balanceexists.Note:Asstudentexperience/training andtime'ermit allinputstothefollowing majorcontrol'systemsandtheirfailureswillbediscussed; 1.ReactorMake-upControl2.SteamGenerator WaterLevelControl3.Electro-Hydraulic ControlSystem10.Title:Accident/Transient Assessment Objective:

Enhancetheabilityforpromptrecognition ofmajoraccident, transients andestablish thebasisfortheappropriate emergency procedures.

TopicSummary:2.3.RodWithdrawal Accidents (FSAR)a.ReviewProtection (DNBRVs.pcm/sec.)

MainGenerator Trips(FSAR)NaturalCirculation, Detaileda.S/Gb,TCalculations b.PowertoFlowRatioc.DecayHeat,d.Subcooling

4.BasisforStoppingRCP'sonLowPressurea.MassInventory b.SteamGenerator Pressure(Bounding Limit)5.S/GTubeRupturea.ImpactofClosingtheMSIVb.MethodsofDepressurizing c.Monitoring Subcooling d.Conditions forStoppingSIe.Conditions Requiring ClosingofPORV6.OnePORVOpenonPressurizer a.DetailsoftheLevelResponse7.SmallBreakTransient BehaviorModesa.<3/8"to>2"b.Conditions forStoppingSI8.SteamBreaka.FSARandGenericAnalysisb.Calculate RCSTemp.for1S/GBlowdown9.MainFeedlineBreaka.Calculate RCSTemp.for1S/GBlowdownb.Calculate TimeforAllS/GtoGoDry10.LossofAllFeedwater a.Calculate TimeforAllSteamGenerators toGoDryb.OptionsAvailable toCoolReactor.(OpeningOnePZRPORV)11.Determination ofInadequate CoreCooling12.AccidentDiagnostics 11.Title:Simulator TrainingObjective:

Observation ofActualAbnormalandAccidentConditions andtheIdentification ofEachTopicSummary:Westinghouse NuclearTrainingCenterControlBoardFamiliarization Demonstrations 1.Verification of:a.NaturalCirculation b.Subcooling c.AdequateCoreCooling IIllV4 2.MajorReactivity Transients a.LoadRejection withRodsinManualb.ATWTc..Continuous ControlRodWithdrawal fromHZP3.Instrument Failures4.SmallandLargeLOCA's5.S/GSecondary Breaks6.Pressurizer PORVOpen7.OneSprayValveOpen8.LossofAllFeedwater 9.LossofRodDriveMG'sTransient Assessment 1.SelectedInstrument Failures2.SelectedAccidents 3.SelectedEquipment.

Failures4.MultipleFailuresAfourweekcourseinnuclearandreactorphysicswaspresented forthoseengineers whodidnothavepreviousnuclearengineering education.

Thiscourse,taughtbyMemphisStateUniversity, ispartofanaccredited collegeprogram,andincludedthefollowing topics:AtomsandMatterLightandElectromagnetic WavesRadioactivity andParticleBehaviorNuclearReactions FissionReactorFundamentals NuclearFissionofUranium-235Neutrons, Reactions, andModerator EffectsNeutronMultiplication FactorsReactivity ReactorKineticsTheSubcritical ReactorOn-the-job

training, including continuing assignment on-shiftasSTA,hasprovidedabasicfamiliarization inplantsystemsandoperation.

Additional TraininExpandedtrainingforthecalendaryear1981willinclude:PlantDesignSystemOperation Transient ResponseAccidentAnalysisSimulator TrainingProcedure ReviewTechnical Specifications Management Skills Requalification trainingwillcommenceJanuary1,1982,andwillcontinueonatwo-yearfrequency (oruntiltheSTAprogramisphasedout).Thisprogramwillinclude:Procedure ReviewTransient ResponseAccidentAnalysisOn-shiftassignment asSTAoron-shiftassignment asSROEvaluations bytheTechnical Assistant forOperational Assessment Lon-TermSTAProramandTraininPlansThelong-term STAprogramwillcontinuetoutilizedegreedindividuals (withthesupplemented education, experience, andtraininglistedabove),orindividuals withanSROlicensewhohavereceivedthenecessary technical education andtraining.

Wewillreplacedegreedindividuals withSRO-licensed individuals asthelicensedindividuals receiveeducation'imilar tothatoutlinedinRG&E'sletterdatedDecember28,1979fromL.D.White,Jr.toMr.DennisZiemann.TheSTAprogramwillbephasedoutwhentheman-machine interface controlroomreviewhasbeencompleted andtheshiftsupervisor andsenioroperatoronashifteachmeettheproposedfutureeducational requirements ofapproximately 60technical credithoursforSROlicensing.

STASelection anduglification Ifreplacement STA'sarerequired, screening willbeperformed toensurecandidates meettheeducation, experience andtrainingrequirements ofourAdministrative Procedure forSTATrainingpriortotheirassignment asSTA.CommentsonINPODocumentandComarisonwithRG&E'sRG&EhasreviewedINPO'sdocumentofApril30,1980concerning STAQualifications, Education andTraining.

Wehaveconcluded thattheseINPOgoalsfortheSTAare"standards ofexcellence" andrepresent anultimategoal.However,lackingguidancefromtheNRConminimumrequirements forSTA,RG&Ehasestablished minimumrequirements for'TA,independent ofINPO's"standard ofexcellence".

i' Wearepleasedtoofferourcommentsontheabove-mentioned INPOdocument.

Wefullyendorsethecommentsandrecommendations madebytheMid-Atlantic NuclearTrainingGroup(MANTG)inaletter,datedOctober21,1980,fromMANTG(Young)toINPO(Thomas)andquotedbelow:GeneralItistheopinionofthemembersoftheMid-Atlantic NuclearTrainingGroupthatthesubjectdocument's experience, education, andtrainingrequirements donotappeartobebaseduponthedemandsoftheSTAposition.

Asanexample,thedocumentincludesapositiondescription whichliststwelvetypicalSTAresponsibilities.

Ofthese,fourpertaintoevaluating plantconditions duringtransients orinvestigating thecausesofsuchtransients'et, verylittleemphasisisplacedontransient conditions inthetransient/

accidentanalysisandEmergency Procedures requirements ofSection6.7.TheMANTGrecommends thatallexperience, education, andtrainingrequirements bebaseduponadetailedjob/taskanalysis'hen derivedinthismanner,thestandards willbeabletorelatetospecificknowledge levels,requirements tothetypicalSTAresponsibilities.

Thisapproachseemsespecially prudentinlightoftherecentemphasisofjobandtaskanalysisbytheNuclearRegulatory Commission, AmericanNuclearStandards Institute, andtheInstitute ofNuclearPowerOperations.

2.Pae10,Section5.2Eeriencea.Thefirstparagraph requirestheSTAtohaveaminimumof18monthsofnuclearpowerplantexperience.

TheMANTGrecommends thatthisrequirement bedeleted.Itisouropinionthataneffective trainingprogramwillproduceacompetent STA,regardless ofhispreviousexperience.

ItshouldbenotedthatINPOdidnotpublishthisrequirement, evenindraftform,untilMayofthisyear.WiththeNRCrequiring fullytrainedSTA'sbyJanuary1,1981,itwillbeimpossible tostafftheSTApositionwithpersonnel whomeetboththerequire-mentsoftheNRCandINPO,unlesstheyaredrawnfromtheexistingplantstaff.b.Paragraph threestatesthatamaximumofthreemonthsoftrainingmaybeappliedtowardtheexperience requirement.

TheMANTGrecommends thatbothon-the-job trainingandplantspecificsystemsoroperations train-ingwhichisconducted byorforthefacilityatwhichtheSTAisqualifying, beequivalent toexperience onaone-to-one basiswithnomaximum.Therationale for l

10thisrecommendation isthattrainingattheplantprovidesthetraineetheopportunity totracesystemsandobserveplantoperations whichtheMANTGfeelsfulfillstheintentofthissection.C.TheMANTGrecommends thattheINPOincludeaprovision inSection5.2whichequatescoldlicensesimulator trainingtooperating plantexperience onathreetoonebasis,similartotheprovision presently allowedforcoldlicenseoperatorcandidates'a ellSection5.3AbsencefromSTADutiesMANTGrecommends thatpersonnel notactivelyperforming STAfunctions butparticipating intheSTArequalification program,beexemptfromtherequirements ofthissection.Additionally, thosepersonsnotperforming thefunctionnorparticipating intherequalification programberequiredtocompleteonlythoseportionsoftherequalification programwhichtheyhavemissedduringtheirabsencepriortoassigning themforSTAduty.Pae13,Section6.1.2ColleeLevelFundamental Education a.IntheElectrical Sciencessection,theMANTGrecommends thatCircuitTheoryandDigitalElectronics bedeletedfromtheknowledge requirements.

TheMANTGdoesnotbelievethattheyarepertinent totheunderstanding ofnuclearpowerplantresponseorcontrol.b.MANTGrequestsguidanceonhowtoobtainthiscollegelevelknowledge withintheshorttimeframerequiredbytheNuclearRegulatory Commission.

Pae15,Section6.2AliedFundamentals-Plant

~SecificTheMANTGrequestsguidanceonhowtodetermine whatconstitutes collegeleveltrainingforPlantSpecifictopics.Pae17,Section6.6General0eratinProcedures MANTGrecommends thatallplantoperating procedures whichrelatetoanSTA'sfunctionbeincludedinthissectionratherthanthoseasmentioned.

Theseprocedures shouldbeidentified intheSTAtaskanalysisrecommended inparagraph

1.

1'C\1IF 8.Pae18,Section6.8Simulator TraininThefirstparagraph requiresatrainee/instructor ratioofnotmorethanfourtoone.Thiswouldseemtorequireatleasttwoinstructors foreverytrainingsessionsinceitisanticipated thatSTA'swillbetrainedalongwiththerestoftheircontrolroomwatchsection.TheMANTGrecommends thata4:1ratioonlyapplywhenonlySTA'sarebeinginstructed inagivencourse.b.TheHANTGrecommends thatsimulator emphasisincludethediscussion anddemonstration ofthoseactionswhichoperators maytakewhichwouldeithermitigateoraggrevate atransient oraccidentcondition.

9.Pae19,Section6.9AnnualReualification TraininMANTGrecommends thatareviewofthetheoretical materialpresented duringSTAqualification beincludedintherequalification program.1.A.1.3ShiftManning~~~~BletterdatYedDecember15,1980fromL.D.White,Jr.toMr.DennisM.Crutchfield, USNRC,RG&Eresponded toshiftstaffingcriteriaandguidelines forscheduling overtimeforlicensedoperators.

Thecommitments pro-videdinthatletter,andproposedalternatives tosomeoftheStaffovertimeguidelines, remainunchanged.

Wehaverevisedadministrative procedures toimplement asimilar'olicy tolimitovertimeworkofpeopleinadditiontolicensedoperators whoperformsafetyrelatedwork.Procedure A52.9hasbeenrevisedtoin-cludelimitsonovertimeworkedbyauxiliary operators inadditiontoSROs,ROsandShiftTechnical Advisors.

Procedure A52.10hasbeenimplemented tolimitovertimeworkedbyhealthphysicist technicians, I&Ctechnicians andkeymaintenance personnel.

GuidancefortheEvaluation andDevelopment ofProcedures forTransients andAccidents TheWestinghouse OwnersGroupwillsubmitbyJanuary1,1981,adetaileddescription ofourprogramtocomplywiththerequirements ofItemI.C.1.TheprogramwillidentifypreviousOwnersGroupsubmittals totheNRC,whichwebelievewillcomprisethebulkoftheresponse.

1plI 12Additional effortrequiredtoobtainfullcompliance withthisitem(withproposedschedules forcompletion) willalsobeidentified, asdiscussed withtheNRConNovember12,1980.DesignReviewofPlantShielding andEnvironmental Qualification ofEquipment forSpaces/Systems WhichMayBeUsedinPost-Accident Operations.

Adiscussion ofourdesignreviewiscontained inaletterdatedDecember28,1979fromL.D.White,Jr.toMr.DennisZiemann,USNRC.Additional information andschedulearecontained inaletterdatedDecember15,1980fromJohnE.MaiertoMr.DennisM.Crutchfield, USNRC.II.E.1.2Auxiliary Feedwater SystemAutomatic Initiation andFlowIndication Part1:Auxiliary Feedwater SystemAutomatic Initiation RG&Ehaspreviously responded toNRCrequirements forauxiliary feedwater systemsinlettersdatedNovember28,1979,December14,1979,December19,1979,March28,1980,May22,1980,May28,1980(2letters)andJuly14,1980.Nochangestotherequirements havebeenidentified whichrequireadditional information.

Part2:Auxiliary Feedwater SystemFlowrateIndication TheDesignCriteriaandFlowDiagramforthemodification oftheAuxiliary Feedwater FlowIndication isprovidedinAppendixA.Someofthesalientfeaturesofthedesignare:2.3.Redundant flowindication isprovidedforeachmotordrivenauxiliary feedwater pump(MDAFP)andthecommondischarge oftheturbinedrivenauxiliary feed-waterpump(TDAFP).Eachredundant channelofflowindication consistsofa:1)qualified transmitter, 2)transmitter powersupply,3)squarerootextractor, 4)outputisolation amplifier, and5)maincontrolboardanalogindicator.

Indication isprovidedtotheOperatorbymeansofadualmovementverticalscaleindicator.

Eachmove-mentreceivestheanalogsignalfromitsrespective channelofflowindication foraparticular A~Nr~-"

13auxiliary feedwater flowpath.Hence,theOperatorcanquicklyascertain ifthereisanydiscrepancy betweenchannels.

4.Eachchannelofflowindication ispoweredfromaseparatebattery-backed vitalinstrument bus.Inaddition, eachflowchannel's analoginstrumentation ismountedinafullyqualified instrument rack.5.Testability featureshavebeenprovidedinthedesign,including localflowindication neartheauxiliary feedwater pumpthatwillfacilitate periodicloopcalibration.

6.TheGinnaStationQualityAssurance Programwillbeutilizedinthedesign,procurement, installation andtestingofthismodification.

7.8.Asmentioned inparagraph 3above,continuous displayofbothchannelsofflowindication willbeprovidedtotheoperatoronthemaincontrolboard.Theflowtransmitters installed asapartofthismodification areincludedinRochester GasandElectric's programofEnvironmental Qualification ofFoxboroTransmitters beingconducted byRG&Eandanumberofotherutilities, andwillbequalified totherequirements ofNUREG-0737.

II.E.4.2Containment Isolation Dependability Thepurgeandventsystemat,Ginnaconsistsoffour48inchisolation valves.TheStaff'sinterimpositiononcontainment purging(nowcalledPosition6)wasim-plemented onthesevalvesbyourDecember14,1979andMay29,1980letters.DuringarecentreviewofPosition6,itwaspostulated thattwo6inchvalvesonourcon-tainmentdepressurization linemaybeinterpreted asfallingunderPosition6requirements.

Thesevalvesarenotusedforcontainment purgeandventoperations butareusedperiodically toequalizepressurebetweeninsideandoutsidecontainment.

Preliminary analysissuppliedbythevendorofthesevalvesindicates thatthemostsevereflowcondition loadingwillnotstressthevalvesbeyondtheirstandarddesignlimits.Theanalysisalsodemonstrates thatthevalveswillcloseasfastorfasterwithflowthanwith-outflow.,Therefore, norestrictions needbeplacedonvalveposition, butaninterimrestriction willbeplacedontheamountoftimethesevalvesareopenuntilthefinalanalysisiscomplete.

PP Avalvequalification programforthese6inchvalveswillbedoneintwophases:Toprovidefurtherassurance ofvalveoperability following post-accident closure,amoredetailedanalysiswillbeperformed.

Thesecondphasewillconsistofseismicandenvironmental qualification oftheentirevalveandactuatorassembly.

Wewillinformyouoftheresultsupontheircompletion.

Thedepressurization valveswillonlybeusedtoequalizepressurebetweeninsideandoutsidecontainment, topreventanunacceptable buildupofcontainment pressureduringnormaloperation.

Whenevercontainment depressurization isrequired, emphasiswillbeplacedonlimitingde-pressurization timestoaslowaspractical.

Wedonothaveatthistimesufficient operating experience withlimiteddepressurization topredictwhatcontainment pressurefluctuations mayoccurduringplantoperation

,tocommittoaspecificdepressurization timelimit.However,allpractical effortswillbemadetolimitdepressurization timestothe90hourperyeargoalwhilecritical.

Shouldthisgoalbeexceeded, wewillinformyouandprovideasummaryofthereasonsforexceeding the90hourgoal.Thecontainment isolation pressuresetpointwillbereducedto4psig.Ourrevisedoperation forcontain-mentdepressurization mayresultincontainment pressures of2psig.Normalinstrument errorsanddriftmayamounttoasmuchas1psig(~1%ofrange).Anaddi-tional1psigmarginshouldbeaddedtoassurethatin-advertent isolation ofcontainment doesnottakeplacesincethissamesignalalsotripsthereactorandstartssafetyinjection.

Wewillcontinuetomonitorcontainment pressure.

Ifitisfeasibletoreducethe4psigsetpointpressure, wewillinformyou.NobleGasEffluentMonitorInformation concerning ourplansformonitoring noblegaseffluents wascontained inaletterdatedDecember15,1980fromJohnE.MaiertoMr.DennisM.Crutchfield, USNRC.Additional information willbeprovidedbyFebruary1,1981.

'h 15II.F.1.3Containment HighRangeRadiation MonitorAVictoreen Model875HighRangeContainment AreaMonitorSystemhasbeenpurchased forinstallation byJanuary1,1982.Thesystemiscurrently beingqualified toIEEE-323andRegulatory Guides1.97and1.89,withtestreportsexpectedtobecompleted byMarch1981.Untilthosetestsarecomplete, however,wecannotcommitthattheinstalled systemwillmeetalloftheNRCrequirements.

II.F.1.4Containment PressureMonitorTheStaffpositionpresently callsfor"continuous recording" ofcontainment pressure; itisfeltthatthiswouldresultinawasteofpaperandunnecessary wearontherecordermechanism.

Asystemisproposed, however,thatwillstartrecording wheneverasafetyinjection orcontainment isolation signalispresent.Thisproposedsystemwillprovideadequaterecording ofsignals.II.F.1.5Containment WaterLevelMonitorInformation concerning RG&Eplanstoinstallcontainment waterlevelinstruments iscontained inRG&ElettersdatedDecember15,1980fromJohnE.MaiertoMr.DennisCrutchfield andNovember19,1979fromL.D.White,Jr.toMr.DennisZiemann.Instrumentation forDetection ofInadequate CoreCoolingRG&E'spositionconcerning inadequate corecoolinginstru-mentation iscontained inlettersdatedDecember15,1980fromJohnE.MaiertoMr.DennisCrutchfield andJuly2,1980fromL.D.White,Jr.toMr.Crutchfield.

1Ji 16II.K.2.13

~~~ThermalMechanical Report--EffectofHigh-Pressure Injection onVesselIntegrity forSmall-Break Loss-of-CoolantAccidentwithNoAuxiliary Feedwater Tocompletely addresstheNRCrequirements ofdetailedanalysisofthethermal-mechanical conditions inthereactorvesselduringrecoveryfromsmallbreakswithanextendedlossofallfeedwater, aprogramwillbecompleted anddocumented totheNRCbytheWestinghouse OwnersGroupbyJanuary1,1982.ThisprogramwillconsistofanalysisforgenericWestinghouse PWRplantgroupings.

Following completion ofthisgenericprogram,additional plantspecificanalyses, ifrequired, willbeprovided.

Aschedulefortheplantspecificanalysiswillbedetermined basedontheresultsofthegenericanalysis.

II.K.2.17 Potential forVoidingintheReactorCoolantSystemduringTransients TheWestinghouse OwnersGroupiscurrently addressing thepotential forvoidformation intheReactorCoolantSystem(RCS)duringnaturalcirculation cooldowncondi-tions,asdescribed inWestinghouse LetterNS-TMA-2298 (T.M.Anderson, Westinghouse toP.S.Check,NRC).Webelievetheresultsofthiseffort,willfullyaddresstheNRCrequirement foranalysistodetermine thepotential forvoidingintheReactorCoolantSystemduringanticipated transients.

Areportdescribing theresultsofthiseffortwillbeprovidedtotheNRCbeforeJanuary1,1982.II.K.2.19 Sequential Auxiliary Feedwater FlowAnalysisTheTransient AnalysisCode,LOFTRAN,andthepresent,smallbreakevaluations analysiscode,WFLASH,havebothundergone benchmarking againstplantinformation orexperimental testfacilities.

Thesecodes,under.appropriate conditions, havealsobeencomparedwitheachother.TheWestinghouse OwnersGroupwillprovideonascheduleconsistent, withtherequirement ofTaskII.K.2.19, areportaddressing thebenchmarking ofthesecodes.

4,C

-17II.K.3.1~~~AndII.K.3.2Installation andTestingofAutomatic Power-Operated ReliefValveIsolation SystemReportonOverallSafetyEffectofPower-Operated ReliefValveIsolation SystemTheWestinghouse OwnersGroupisintheprocessofdeveloping areport(including historical valvefailureratedataanddocumentation ofactionstakensincetheTMI-2event,todecreasetheprobability ofastuck-open PORV)toaddresstheNRCconcernsofItemII.K.3.2.

However,duetothetime-consuming processofdatagathering, breakdown, andevaluation, thisreportisscheduled forsubmittal totheNRConMarch1,1981..AsrequiredbytheNRC,thisreportwillbeusedtosupportadecisiononthenecessity ofincorporating anautomatic PORVisolation systemasspecified inTaskActionItemII.K.3.1.

II.K.3.5Automatic TripofReactorCoolantPumpDuringLossofCoolantAccidentTheWestinghouse OwnersGro'presolution ofthisissuehasbeentoperformanalysesusingtheWestinghouse SmallBreakEvaluation ModelWFLASHtoshowampletimeisavailable fortheoperatortotripthereactorcoolantpumpsfollowing certainsizesmallbreaks(SeeWCAP-9584).Inaddition, theOwnersGroupissupporting abestestimatestudyusingtheNOTRUMPcomputercod'etodemonstrate thattrippingthereactorcoolantpumpattheworsttriptimeafterasmallbreakwillleadtoacceptable results.Forbothoftheseanalysisefforts,theWestinghouse OwnersGroupisperforming blindpost-test predictions ofLOFTexperiment L3-6.TheinputdataandmodeltobeusedwithWFLASHonLOFTL3-6hasbeensubmitted totheStaffonDecember1,1980(NS-TMA-2348).

Theinformation tobeusedwithNOTRUMPonLOFTL3-5willbesubmitted priortoperformance oftheL3-6testasstatedinWestinghouse OwnersGroupletterOG-45datedDecember3,1980.TheLOFTprediction frombothmodelswillbesubmitted totheStaffonFebruary15,1981giventhatthetestisperformed onschedule.

Thebestestimatestudyisscheduled forcompletion byApril1,1981.Basedonthesestudies,theWestinghouse OwnersGroupbelievesthatresolution ofthisissuewillbeachieved pVI 18-without,anydesignmodifications.

Intheeventthatthisisnot,thecase,aschedulewillbeprovidedforpotential modifications.

II.K.3.12 ConfirmExistence ofAnticipatory ReactorTripUponTurbineTripAnanticipatory tripuponreactortripexistsattheR.E.Ginnaplantasshownindrawing882D612,Sheet2,Revision3andSheet3,Revision2,providedwithaletterdatedJanuary18,1979fromL.D.White,Jr.toMr.DennisZiemann.II.K.3.17ReportonOutagesofEmergency CoreCoolingSystemsInformation onECCSequipment outagesiscontained inTableII.K.3.17.

Theinformation inTableII.K.3.17 wascompiledinresponsetoMr.D.G.Eisenhut's May7,1980letterconcerning FiveAdditionTMIItemsanddoesnotincludethecorrective actiontaken,arecentchangeintherequirements.

Nevertheless, asseenfromthetable,most.outagesweretheresultofroutinemaintenance andinspections.

Incaseswhereaviolation ofTechnical Specifications didoccur,thecorrective actiontakenisdocumented inLicenseeEventReportsfiledwithNRC.WehavereviewedtheECCSequipment outagesanddetermined that.noactionisrequiredatthistime.Malfunctioning steamadmission valves,thecauseoflengthyturbine-driven auxiliary feedwater pumpoutages,werereplacedinMay,1980.'Improving LicenseeEmergency Preparedness

-LongTermAtthistime'ebelievewewillbeabletocomplywiththeimplementation scheduleestablished forthisitem.However,weplantocomplywiththerequirement forapromptnotification systemprimarily withtheinstalla-tionofsirens.Wedonotyethaveacommitment forsupplyofthesirensbecausefieldworknecessary toestablish soundlevels,sirenlocations andthenumberofsirensrequiredisnotyetcompleted.

Ifitbecomesnecessary torequestanextension oftheimplementation dateasthisworkproceeds, wewillnotifyyoupromptly.

4 19Theemergency plansrequiredtobesubmitted byJanuary2,1980concerning radiological emergency responseplanswillbeprovidedbyseparatecorrespondence.

III.D.3.4 ControlRoomHabitability Requirements Theinformation requested inAttachment 1toitemIII.D.3-4 isnotbeingsubmitted byJanuary1,1981forthereasonsgiveninaletterdatedNovember24,1980fromL.D.White,Jr.toMr.DennisM.Crutchfield, USNRC.

TABLELI.K.3.17 KUIPMBlTREASOHIHOPHQBIB DATEIHOPHfABIR PI>AHTTIHEOP1HATIffG IHOPHMfiE ffODE*T.S.TIMEALTDWANCE DATEOPHQBIETIME)OHRABIZAHfHPumpM-11.15Inspection andMaintenance Bus14Supplyfrom1ADieselN-15&t:H-52.1BreakerInspection aMaintenance BAux.F.W.PumpH-11.5cMaintenance EndBearingCoverGasketfAContSprayPumpDischarge N-64.1Defective

'A'ontact Valve860A-Manualopencurcuit6/14/767/9/767/20/768/2/76111024Hrs.N/A24Hrs.6/14/767/9/767/20/768/2/V61811151015K141211Hours11Hinutes5Hours4Mimtes4Hours20Minutes4Hours27MinuteTurbineDriveAPWPAComponent CoolingPumpBDieselGenerator AServiceWaterPump*'ServiceWaterPumpBServiceWaterPumpMaintenance-ftydraul icControlValve.N-11.27&cH-.45.1AInspection

&:Naintenance Bus16Breaker-Replaced Secondary ContactsM-ff.100,H-45.1APrrmpardMotorInspection

&cMaint.M-11.10&r.H-45.1APumpardMotorInspection ScHaint.M-11.10&r.H-45.1APumpardMotorInspection 4Maint.7/22/768/17/768/21/7611/4/7611/5/7611/9/76C.S.DC.S.DN/AN.A.N/AH/AN/AN/A7/25/768/20/V68/22/V611/4/7611/8/7611/9/7617001530f1'51512452IHours5Minrteo81Hours50Minutes18Hours27Hfmrtes6Hours45Minutes78Hours59Himrtes5Hours45MinutesAOV~6AFromSprayAddativeYIC-836AController Failure.TankNaOH11/17/76110024Hrs.11/17/767Hours30Minutes*0-Plantoperating atpower;C.S.D.-ColdShutDown;H.S.D.-.HotShutDown**Ginnahas&rServiceMaterPumps.Onlytwoarerequiredforpost-accident operation

{FSARTable9.6-1)Sheet1of12

TABLEII.K.3.'17 (Cont'd.)

EQJIPHBIT CServiceWaterPumpAServiceWaterPumpCServiceWaterPumpBServiceWaterPump1CSISPumpBus14BreakerRPASONINOPEBABLB M-11.10&:M-45.1APumpendMotorInspection andMaintenance (M-32,M-32')

AI&0onBreaker{M-32,M-32')

AI&0onBreakerBreakerAI&0Inspection ReplacedSecondary ContactsonBreakerDATEINOPHQBIB 11/9/763/28/773/28/773/24/771/3/vvTIMEINOPHQBIB 1515PLANTOPERATINB MODET.S.TIMEALIDWANCB N/AN/AN/AN/A24Hrs.DATEOPERABLB12/21/763/28/773/28/773/24/vv1/3/vvTIMEOPHUQKB1245152514501150TIMEOUPOPSERVICE41Bys21Hours30Mimtes35Mirutes1Hour50Minutes1Hour50Mimtes2Hours50MinutesBServiceWaterPumpDiverscleaningsuctionscreen1BBoricAcidTransferPumpBreakerPulledtoPerformMaint.onC.B.Sritch.6/1o/77103024Hrs.N/A3/7/776/1o/vv114511003Hours15Minutes30MirutesA&9ServiceWaterPumpsCSISPumpBus14BreakerDServiceWaterPumpDiverscleaningsuctionscreenBreakerfailedtocloseduringP.T.DiverscleaningsuctionscreenCheckValveleaking6/10/776/29/776/9/77v/>>/771430N/A24Hrs.N/A24Hrs.6/1o/vv6/29/776/9/vvv/>>/vv1020172019451Hour20Mimtes3Bours50Minutes2Hours30Minutes5Hours15Minutes*+*AI&0-AnnualInspection andOverhaulSheet-2of12 S

TABLEII.K.3.17

{Cont'd.)

KQIPM1I1T REASONINOPERABIB PLANTDATETINEOPERATING INOPERABLE INOPHQBLB NODET.S.TIMEALMNANCEDATEOPERABLETINEOVPOPSERVICETurbineDrivenABFBoricAcidPumpsEcCVCSValvesScPipingSteamedmission valveproblemMOV3504RepairValves398ABB6/1/778/23/vv1140N/AN/A7/11/7714008/23/vv152540Days2Hours20Mimtes40MinutesBD/GBus16Breaker1AComponent CoolingPumpAServiceWaterPumpBComponent CoolingPumpBComponent CoolingPumpNa51TankIsolation ValvesBreakerwouldnotcloseCalibration ofpresstransmitter Scheduled MotorOverhaultocheckcouplingalignment CheckCouplingAlignment RepairValvesIsolatedtorepairleaks9/14/7707069/26/77110610/19/77070011/15/VV080011/16/Tl130012/3/77010012/3/770100H.S.D.H.S.D.168Hrs.24Hrs.N/A24Hrs.24Hrs.48Hrs.48Hrs.9/14/7710309/26/VV133011/8/7l11/15/77171911/16/771445'12/3/Yl144512/3/7714453Hours24Nimtes2Hours24Minutes20Days6Hours9Hours19Minutes1Hour45Mimtes13Hours45Minutes13Hours45MirutesBCharcoalfilter(CRecircPans)LowAirPlowAlarm1/6/78213524Hrs.1/v/v8164119Hours.6MinutmSheet3of12 f'It TABLEII.K.3.17 (Cont'd.)

EVIPMENTBServiceWaterPumpRotorOverhaulDATETIMEINOPHUSIR INOPHUSIB 12/12/770930KQiTOPERATING MODET.S.TIMEALTlSANCE N/ADATEOPHEEBIE1/6/78TIMEOPHQBIRTIMEOUPOPSERVICE25Days1Hour43MitutesAServiceWaterPumpDServiceWaterPumpBreakerInspection BreakerInspection 3/16/Vs09003/16/781445N/AN/A3/16/7814403/16/7815305Hours40Minutes45MinutesBServiceWaterPumpBreakerInspection 3/14/781245N/A3/14/Vs15252Hours40MirutesCServiceWaterPumpCServiceWaterPumpAServiceWaterPumpBDieselGenerator BreakerInspection CleanIntakeScreenCleanIntakeScreenInspection 3/14/7815155/26/78C8455/26/7808453/27/VS0400C.S.D.N/AN/AN/AN/A3/14/7816035/26/7812505/26/vs3/31/78165648Mirutes4Hours5Minutes4Hours5Minxtes4Days12Hours56MimtesC.ServiceWaterPumpValve860BDischara:

fromContainment SprayPumpWorkcnexpansion Joint5/3/781030Valvewouldnotstrokeclosed6/29/781230N/A24Hrs.5/4/7810106/29/78124523Hours40Minutes15MinutesAServiceWaterPumpInspection 4lubrication 6/7/781120N/A6/7/781448'3Hours28MinutesSheet4of12

/Jp TABLEIZ.K.3.17 (Cont'd.)

EQHPMFNTDATETIMEINOPPIABLE INOPERABIR PLANTOPFRATI?6 MODET.S.TIMEALMWANCEDATEOPPRABLETIMEOPERABLETIMEOUPOFSERVICEDServiceWaterPumpInspection 8cLubrication

.6/7/781525N/A6/7/7814471Hour22MinutesBServiceWaterPumpCServiceWaterPumpHoldforMaintenance Holdforl1aintenance 6/v/vs11006/7/780650N/AN/A6/V/Ve6/7/7811205Hours30Mirntes20MitutesAServiceWaterPumpTochangeexpansion

]oint5/2/78N/A5/2/781700BContRecircPansReplaceO.B.fanbearing5/10/780600H.S.D.N/A5/11/78.140052HoursBDieselBus16Breaker1DContainment RecircPanBreakerD.C.ControlMalfunction CableInspection 8/16/7807009/8/7814300168Hrs.8/16/781030144Hrs.9/8/7815245Hours50Minutes54MinutesAContainment RecircFan1ARHRHXOutletHCVA25MOV852A(RIB)BentController Arm84-209(Splices) 8/51/7811009/20/780851Toinstallsplicingsleeves9/18/78082012Hrs.12Hrs.8/51/7814009/20/Ve1500144Hrs.9/18/781f505Hours10Mimtes5Hours6Hours9MinutesMOV852B(RHR)H4-209(Splices) 9/19/78091512Hrs.9/19/7815156HoursCContainment RecircPanDServiceWaterPumpsplicingleadsreplacebearing9/27/78114510/16/780915N/A10/16/781430144Hrs.9/2l/7816475Hours2Mimtes5Hours15MinutesSheet5of12 k

TABLEXX.K.3.17 (Cont'1.)

S@IPMBiTDATETIMEINOPHUSIE INOPERABLE PLANTOPHQTINQMODET.S.TIMEAIIDWANCE DATEOPHQBLETIHEOPERABIBTIMEOUIOFSERVICEBServiceWaterPumpMotorvibration 12/15/780845N/A12/15/7816417Hours56Minutes8Containment RecircPumpTurbineDrivenAFWPDContainment RecircFansAContainment RecircFansneedssplicesInspection checkforoilleakssplicessplicinginstallsleeves9/28/V8OVOO4/2/7807009/22/7807009/26/780600144Hrs.9/28/78'I332N/A11/2/781410144Hra.9/Zl/781140168Hrs.9/26/7812156Hours32Mimtes7Hours10Minutes124Houn340Hi>utes6Hours15Minutes1CSIPump(Bus14)StartFailure1/3/V924Hra.1/3/7912551Hour58Mimtes1ADieselGenerator HOV851B(R1E)wouldnotre-open2/6/79JjubeOilCoolerHiOP**"*1/8/790905Coastdawn 123012Hra.2/6/7917157Days1/8/793Hours25Minutes1Hour15MimtesADieselGenerator PT-12.12/6/7907007Days2/6/7909352Hours35Minutesoverpressure protection systemBServiceWaterPumpMaintenance onvalvePCV431CInspectMotorBearings6/6/791015V/1V/V90700C.S.D.8Hrs.N/A7/17/7914556/11/7911107Hours55Hirutes5Days55Minutes*+**OP-OilPressureSheet6of12 rIJ TABLEXX.K.3.17 (Cont'd.)

DATETIMEINOPERABIR INOPHtABIS KANTOPFRATIt6 MODET.S.TIMEALMWANCEDATEOPZRABIRTIMEOPBRAESPORVoverpressure protection sys4304431CMOV5I5&5t6closed7/18/790710C.S.D.8Hrs.7/18/79.13146ttours4MinutesOverpressure Protection Sys.PCV430Mov516closedslightleakage7/18/791413C.S.D.7Days7/18/7915401Hour27MimtesBServiceWaterPump1CServiceWaterPump1DServiceWaterPumpContSprayPumpDischargs Valve860CAServiceWaterPumpTurbineDrivenAux.PWPumpTurbineDrivenAux.Peed.PumpChangeOilChangeOilChangeOildidnotcomeoffseatonfirsttrySteamAdmission Valve3505MotorInoperative MOV3505didnotopenproperly7/26/7908307/25/7908>>7/24/7903304/24/7910486/18/7906308/2/7919158/4/791300C.S.D.C.S.D.C.S.D.H.S.D-toC.S.D.N/AN/AN/AN/AN/AN/A7/26/7913207/25/7913457/25/7908I34/24/79l05'37/12/7913128/3/7920508/Zl/7914504Hours50Minutes5Hours32Mimtes28Hours43Minutes5Minutes26Days6Hours42Minutes1Day1Hour35Mimtes23Days1Hour50Mirutes1AComponent CoolingWaterPumpsvitchinPull-Stop forperformance ofCP-617.09/7/79111024Hours9/7/79112513MimtesSheet7of12; fj TABLEII.K.3.17 (Cont'1.)

REASONINOPHQBIB DATETINEINOPERABIR INOPHQBIR KANTOPI3ATING NODET.S.TIMEAIZOWANCE DATF,OPERABIRTIMEOPERABIRTIMEOROPSERVICEBDieselGenerator DieseltobreakertoBus16wouldn'tclose9/13/7905557Days9/13/7909303Hours35Minutes1A11otorDrivenAux.PeelPumpPipssupportsremoved8/29/791100N/A9/4/7915306Days4Hours30MinutesTurbineDrivenAux.PeedPump1BEmergency DieselGenerator "D"StandbyAPPBDieselGenerator SteamDrivenA.P.P.PowerSupplytoV-3996TurbineDriven1%lP1BAux.Peed.Pump1AAux.FeedPump"C"Containment Recirc.FanPumpwillnotoperateundersteadystateconditions Naintainance (Cleanoilcooler)IooseAnchorBoltscleaninletcoolerHain'tenance RewiringPTCalibration CP-2001IewFlowAlarm9/10/7911309/24/7907309/9/79152010/16/79202010/17/79112011/5/79084011/16/79101511/16/79135211/1'7/79 223007Days9/14/7914507Days9/29/7914007Days9/20/7914007Days10/16/7923507Days10/18/7915207Days11/15/7911207Dsys11/16/7912007Days11/16/7916007Days11/18/7910504Days3Bours20Minutes5Ihgrs6Hours30Minutes22Hours40Mirutes3Hours30MinutesKHours2Hours40Hirutes1Hour45Hinutes2Hours8Mitutes12Hours20MinutesSheet8of12 l>>

TABLEII.K.3.17 (Cont'd.)

IQlIPMENT REASONINOPFRABIB PLANTDATETINEOPERATING INOPHlABIB INOPHlABIR HODBT.S.TIMEALIDWANCB DATEOPERABLBTIMEOPHlABIBTIHBIJPOPSERVICESteamDrivenAux.Peed.PumpSteamDrivenAux.Peed.PumpN2Accumulator forPCV-430(V801APressure)

PROVBoricAcidStorageTanks"B"ServiceWaterPump"A"DieselGenerator "1D"ServiceWaterPump1ARHRPump1BRHRPump"1C"StandbyAux.PeedPump"D"StandbyAux.FeedPumpFieldPT-16ClosedgovernervalveinordertoisolateSteamBlowdown(BD)TankInxN2PressurebecauseofV-8600ArepairB.A.ppmbelowspecs.NoiseinmotorWouldnotacceptmorethan1KOkwHoldforpumprepacking ChangeOil,installThermocouplesChangeOil,installThermocouples 11/19/79131512/2/79114512/9/79'200>>/n/7908301/18/8007101/22/8006102/8/8010302/8/8012312/19/8010002/21/80083012/17/791340.C.S.D.7DaysN/AN/A241hurs24Hours11/19/79134012/3/79040012/10/79124812/19/7913151/15/8010101/18/8012501/22/8014552/8/8O2/8/8014362/20/8015002/22/8)111025Hirutes16Hours15Minutes24Hours48Hinutes47Hours'35Mirutes49Days1Hour40Hirrrtes51kers40Hinutes8Hours45Minrtes2Hours2Hours5Minutes26Hours40MinutesSheet9of12 4J TABLEII.K.3.17 (Contrd.)

MIIPNENTRFAHONINOPH1ABLFi DATEINOPERABLE PLANTTIMF.OPFRATINGINOPNABLFi MODET.S.TIMF,ALIOWANCE DATEOPERABLFi TINFiOPERABMTIMEOUZOFSERVICE"C"StandbJJAux.FeedPumpChangeOil3/17/M08203/21/M110098Hours40MinutesMOV-73%CCtoRllR11X"A"RllRPrrmp"1B"BoricAcidPumpClutchproblemwithLimitorriue LeakingHealReplacement ofPT-110(N-12.1)5/12/805/17/805/19/8022101150H.S.D.C.S.D.N/AC.S.D.N/A5/12/805/19/805/19/M21301Hour35Mirutes53Hours5Minutes9Hours40Mirutes"1A"BoricAcidPumpNOV-3505h hTurbineDrivenAux.FeedPump.llOV-3504A MainSteamfrom1BStadiaGenerator toAFPBoricAcidStorageTankBoricAcMStorageTankBoricAcidStorageTanksAccumulators BoricAcidStorageTanksReplacement ofPT-110(N-12.1)Ground.inMotorGroundedMotorIxrwConcentration TankA-12.9fTankB-11.85LowConcentration TankA8cB-11.%llighConcentration TankAM-13.0fLeveldroppedto48r'owConcentration (11.9)to(11.8r')5/19/M5/22/8O5/22/eo4/20/794/16'?98/31/795/22/eo7/11/8O115011301015145015'301045C.S.D.*H.S.D.H.S.D.H.S.DN/AN/AGotoH.S.DGoToC.S.D1lhurGoToH.S.D5/19/805/22/eo5/22/eo4/20/V94/16/79e/31/V95/22/M7/11/M2130135017351440161515539Hours40Minutes2Hours20Mirutes3lhurs35Minutes2Hours45Mirutes1Hour50Minutes4Hours6Mirutes45Mirutes5Hours8MinutesSheet10of12 eTABLEXI.K.3.17 (Cont'd.)

REASONBSPHQBIBDATEINOPHQBIB TIMEINOPERABIE KANTOPHATING5$DET.S.TIMEALIOWANCE DATBOPERABIETIMEOPBRAKETIMEOGPOPSERVICEBoricAcidStorageTanksHighConcentration (14.4$)7/14/M1020GotoH.S.D7/14/8015305Hours10Minutes"B"BoricAcidStorageTank"A"ServiceWaterPumpMinorMaintenance v/e/80hwConcentration (11.8r')7/14/800820N/A7/8/MGotoH.S.D7/14/8013401Hour35Mirutes5Hours20Minutes"D"StandbyAux,P.W.Pump"C"StandbyAux.P.W.PumpN-11.14AnnualInsp.andmaintenance M-11.14AnnualInsp.andmaintenance 6/24/806/25/M11107Days6/25/80v~6/27/801015142733Hours15Nirutes51Hours17Minutes"D"ServiceWaterPump"D"ServiceWaterPump1BEmergency DieselGenerator "A"Aux.P.W.Pump(NotorDriven)Minorinspection 7/3/80M321~DB25~D~~DB75CircuitBreakerNaintROCTripDeviceTestand/orRe-placement 9/10/80CP2001.01AMotordriven9/8/MAux.PW.Pumpdischarge flrnrloop2001M-11.10.1 MinorInspection 7/30/MN/Av/3/MN/AV/30/M7Days9/8/M7Days9/10/801425102914406Hours25Hirutes5Hours59Minutes4Hours41Hirutes5Hours45Minutes"D"ServiceWaterPumpM-11-10.1 MinorInspect.ofSWPPackingleak8/19/80N/A8/20/M131513Hours45MinutesSheetllof12 k~

TABLEIX.K.3.17 (Cont'd.)

"1B"Emergency DieselGenerator ABnergency DieselGener-atorH-32.1,DB-25,DB-50,DB-75circuitbreekermaintenance andOCTripDeviceTestandforreplacement Operability Questioned seeLER80-9DATEINOPHQBIR 9/10/8010/3/80PLANTTINEOPERATING INOPERABLE HODET.S.TINEALIlNANCE DATEOPERABLE9/10/8)10/3/8)TINEOPERABIB1113TINEOUPOPSERVICE4Hours41Hinutes1Day4Hours24HinutesTurbineAux.Peedwater PumpSN-79-1832,B10/2/80010/3/8011153Hours15HimtesSpraySystemToAPPOilresorvoir SN-83-1833.6 Installation ofAux./Int.

BuildingLoopPireSupression Valves10/20/8010/25/804Days21HoursSheet12of12 f~

APPENDIXADesignCriteriaAuxiliary FeedPumpInstrumentation UpgradeGinnaStationRochester GasandElectricCorporation 89EastAvenueRochester, i4ewYork14649ENR-1869Revision1May5,1980Preparedby:0,Responsilengineersin(seDATEReviewedby:QuatyAssurance

Engineer, Designl380DATEApprovedby:0I/IManager,Mechanical Ehgineering DATEPage4292 I"lF

~~RevisionStatusSheetPapeLatestRev.PageLatestRev.PageLati.stRev.sign.CriteriaEWR1869PageiiRevision5/5/804291

~~

'DesiCriteria1.01.1.11.1.2SummarDescritionoftheDesiSummaryThepurposeofthismodification istoupgradetheflowandpressureinstrumentation associated withthemotordrivenandturbinedrivenauxiliary feedwater pumpsatGinnaStation.Thismodification involvesthereplace-mentofthefollowing primaryinstrumentation:

PT-2029,FT-2001,FT-2009,PT-2019,PT-2030,FT-2002,FT-2006,FT-2007.Thisinstrumentation presently useddoesnot,havethedesiredaccuracyandrepeatability.

Inaddition, theexistingflowtransmitters areutilizedtooperatevalves4007,3996and4008.Eachoftheseflowtransmitters haveabuiltinswitchwhichisactuatedviaamechanical linkage.Thismechanical linkagehasenoughinertiasuchthataccurateandrepeatable determination ofswitchactuation pointisnotpossible.

Aspartofthismodification, theseswitcheswillbereplacedwithelectronic bistables, whichelectronically compareflowtransmitter outputwithsetpointandchange'statewhenthesetpointisreached.1.21.2.1Tosatisfytherequirements ofreference 2.5below,additional channelsofflowinstrumentation willbeaddedtoeachauxiliary feedwater pump.Thisadditional channelwillbeoftheoppositechanneldesignation fromthatoftheprimarychannel.Theprimarychannelforeachfeedwater pumpwillcontrolthatparticular pump'sdischarge valve,whereasthesecondary channelmerelyindicates flow.Thesecondary channelasshownontheabovereferenced consistsofthatinstrumentation withouttagnumbers.Functions (Reference RGSEdrawing33013-697, Rev.0)tPoopFT-2001Thisloopmeasurestheflowinauxiliary feedwater linetothe"A"steamgenerator, Thedifferential pressuremeasuredbyFT-2001isconverted toaflowsignalby.FM-2001.Indication offlowonthemaincontrolboardisprovidedbyFI-2021A.

FM-2001Aactsasanisolation amplifier toisolatetheclassIEsystemfromFI-2021Bwhichisnotsafetyrelated.Electronic bistableRevisionFY-2001functions topositionvalve4007suchthattheflowmatchesFY-2001's setpoint.

FQ-2001suppliesdcpowertothisloop.DesignCriteriaEWR1869Page1Date4290

'rT.

1.2.2LoopFT-2009Thisloopmeasuresthetotaldischarge flowofthesteamdrivenauxiliary feedwater pump.FT-2009measuresthedifferential pressureacrossitsflowelementandFM-2005convertsthissignaltoaflowsignal.FY-2005isanelectronic bistablewhichopensrecircvalveCV-27tomaintainminimumflowthroughthepump,duringlowflowoperations.

FM-2009Aisanisolation amplifier whichisolateslocalflowindicator FI-2009fromtheClassIEsafetysystem.FQ-2009suppliesthisloopwithdcpower.1.2.31.2.41.2.5loopFT-2002Thisloopfunctions exactlythesameastheFT-2001loopwiththeonlydifference thatthisloopmonitorstheflowofauxiliary feedwater totheBsteamgenerator.

LoopsFT-2006andFT-2007Boththeseloopsfunctioninthesamemanner;eachloopmeasurestheflowtoitsrespective steamgenerator fromtheturbinedrivenauxiliary feedwater pumpandindicates thisflowonthemaincontrolboard.Anisolation amplifier foreachloopisolatestheclassIEportionfromthenonsafetylocalindication locatedneartheturbinedrivenpump.Eachloopalsocontainsadcpowersupply.LoopsPT-2029,PT-2019andPT-2030Eachoftheseloopsaresimilarandmerelymonitorthedischarge pressureoftheirrespective auxiliary feedwater pump.Indication ofdischarge pressureforeachpumpisonthemaincontrolboard.1.2.61.3ForloopsFT-2001,FT-2009andFT-2002asecondary redundant channelofflowinstrumentation isprovided.

Eachchannelconsistsofaflowtransmitter (FT),sguarerootconverter (FM),powersupply(FQ)andcontrolroomflowindicator (FI)..Performance Reguirements Thesensingelements(theflowandpressuretrans-mitters)shallbecapableofsensingandproducing anoutputovertherangeofdesignvaluesforallpossibleoperating andaccidentconditions fortheparticular systeminwhichtheyareinstalled.

DesignCriteria~~EWR18692PageRevisionDare5/5/804290 CJ~~ET Control1.51.5.11.5.22.0AsoutlinedinSection1.1above,thismodification willreplacetheintegralflowswitchesintheflowtransmitters withelectronic bistables.

Thismodifica-tionshallinnowayaffectthecontrolofthesevalves.ModesofOperation TheclassIEportionofthismodification shallbedesignedtobeoperational:

1)duringallmodesofnormalplantoperation, 2)afterasafeshutdownearth-quake,and3)afterasteam/feedwater linecrackbreakeventintheIntermediate Building.

ThenonClassIEportionofthismodification shallbedesignedforoperations duringstartup,hotshutdown, andpoweroperations.

ReferencedDocuments 2.12.22.2.12.2.22.3Rochester Gas&ElectricCorporation, GinnaStationQualityAssurance Manual,AppendixA,"QualityandSafetyRelatedListingandDiagrams",

October1,1976.USNRC'egulatory Guides.No.1.29,"SeismicDesignClassification",

Rev.2,February, 1976.No.1.100,"SeismicQualification ofElectricEquipment.

forNuclearPowerPlants",Rev.1,August,1977.AmericanNationalStandards Institute.

ANSIN45.2.2-1972,"Packaging,

Shipping, Receiving, Storage.andHandlingofItemsforNuclearPowerPlants".2.42.4.12.4.22.4.3Institute ofElectrical andElectronic Engineers Standards.

IEEE-323-1974,"Standard forQualifying ClassIEEquipment forNuclearPowerGenerating Stations".

IEEE-344-1975,"Recommended Practices forSeismicQualification ofClassIEEquipment forNuclearPowerGenerating Stations".

IEEE-323-1971, "Standard forQualifying Class1EEquipment forNuclearPowerGenerating Stations" Revision2.4.4IEEE-344-1971, "Recommended Practices forSeismicQualification ofClass1EEquipment forNuclearPowerGenerating Stations".

DesignCriteriaEWR1869Page342.90 C'.~r~

2.4.5~~2.4.6IEEE-383-1975, "IEEEStandardforTypeTestofClassIEElectricCables,FieldSplicesandConnections forNuclearPowerGenerating Stations".

IEEE-384-1974, "TrialUsetandardCriteriaforSeparation forClassIEEquipment andCircuits".

2.4.72.53.03.14.05.06.06.1IEEE-336-1977, "Installation, Inspection andTestingRequirements forInstrumentation andElectricEquipment DuringConstruction ofNuclearPowerGenerating Stations".

LetterdateNovember19,1979toD.Ziemann,NRRfromL.D.White,Jr.section2.1.7.b.SeismicCateorBasedonUSNRCRegulatory Guide1.29andAppendixAoftheGinnaFSARthefollowing instrumentation isSeismicCategory1:FT-2001,FM-2001,FM-2001A, FI-2021A, FQ-2001,FY-2001,FT-2002,FM-2002,FM<<2002A, FI-2022A, FQ-2002,FY-2002,FT-2006,FM-2006,FM-2006A, FI-2023AFQ-2006,FT-2007,FM-2007,FM-2007A, FI-2024A, FQ-2007IPT-2029,PI-2189A, PQ-2029,PT-2019,PI-2048A, PQ-2019,PT-2030,PI-2190A, andPQ-2030,andallinstrumentation usedaspartoftheseondarychannelflowindication.

BasedonUSNRCRegulatory Guide1.29andAppendixAoftheGinnaFSARthefollowing instrumentation isnotSeismicCategory1:FI-2021B, FI-2023B, FI-2024B,

.andFI-2022B.

ualitGrouNotApplicable.

CodeClassNotApplicable.

Codes,Standards andReulatorReirementsThenonsafetyrelatedportionofthismodification shallbeinstalled aspertherequirements oftheNationalElectrical Code,1978.USNRCRegulatory Guide1.100definesadditional require-mentsandchangestoIEEEStandard344-1975, "IEEERecommended Practices forSeismicQualification of6.2ClassIEEquipment.

forNuclearPowerGenerating Stations".

Implementation ofthisstandardforprocurement ofClassIEinstrumentation willincludetherequirements ofthisRegulatory Guide.DesignCriteriaRevision1EWR1869Page4Date55804290 p

6.37.07.17.1.27.1.37.1.47.27.3FluidPressure1550psigFluidTemperature 40to120'F.Current,10to50mAdcElectricInstrumentation Current,10to50mAdcInstrumentation PowerSuppliesIEEE-336-1977 shallbeusedasaguideline duringtheinstallation, inspection andtestingphaseofthismodification.

DesiConditions FlowandPressureTransmitters 7.3.17.3.27.3.39.0InputVoltage118volts60hz1POutputCurrent10to50mAdcMaximumLoadLoadConditions 660ohmsTheinstrumentation listedinSection3.1shallbedesignedtowithstand theeffectsofasafeshutdownearthquake (0.2gbasegroundmotion)withoutalossoffunction.

Environmental Conditions 9.19.1.19.1.29.1.39.1.49.29.2.19.2.29.2.3Intermediate BuildingTemperature PressureRelativeHumidityRadiation ControlRoomTemperature PressureHumidityNormal40to104Fatm.0to100%Accident.

215oF1.0psig100%65to85F.atm.15to95%40to120'F.atm.15to95%(5R/hr-gammaaccumulative)

DesignCriteria~~~EWR1869Page5RevisionDate5/5/8042.90 C/~~C/~"54 9.2.49.39.3.19.3.29.3.39.3.4Radiation RelayRoomTemperature PressureHumidityRadiation negligible 40to104F.atm.15to95%negligible negligible 40to104F.atm.15to95%negligible 9.4Newpressureandflowtransmitters requiredbythismodification shallbeenvironmentally qualified toIEEE-323-1971 andIEEE-344-1971.

9.5Newprocessanalogcomputational equipment shallbeenvironmentally qualified inaccordance withIEEE-323-1974 andIEEE-344-1975.

10.0Interface Reirements10.110.211.012.0Existingcabletraysutilizedasaroutingpathforthismodification shallbereviewedtoensurethattraycapacityisnotexceeded.

Mountingofnewelectronic instrumentation inexistingracksintheRelayRoomshallnotdegradethecapability ofthoserackstowithstand theeffectsofthesafeshutdownearthquake.

MaterialReirementsNone.Mechanical Reirements13.0Flowandpressuretransmitters shallbedesignedforinstallation atthelocationoftheexistingtransmitters, andutilizing existingtubingconnections.

Structural Reuirements 14.015.0None.HdraulicReuirements None.ChemistrReirements~~~None.DesignCriteriaEWR1869Page6Revision4290 Ait l6.016.1Electrical Reuirements Instrument cableutilizedinthismodification shallmeetthefollowing requirements:

16.1.1Size16AWG.16.1.2Voltagerating600volts.16.1.3Insulation shallbequalified aspe'rIEEE-383-1975.

16.2Instrument powershallbefroma120VAC,60ha,lpClass1Epowersupplyasfollows.16.2.1Primaryinstrumentation power:fromsameinstrument busasmotor(turbine) controls16.2.2Secondary flowindication:

fromoppositeinstrument.

busdesignated by16.2.1above17.00erational Reirements18.0Thismodification shallnot.imposeanyadditional operational requirements underallmodesofplantoperation asthismodification willnotchangeorintroduce anyadditional equipment operations orcontrol.Instrumentation andControlReuirements 19.0Theinstruments utilizedinthismodification shallhavethesamebasicspan,range,andindication astheexistinginstrumentation.

AccessandAdministrative ControlReirements20.0None.Redundanc

,DiversitandSearationReuirements Separation betweenseparation groups1and2shallbemaintained asperIEEE-384-1974 wheneverexistingplantdesignpermits.Whereseparation betweengroupscannotmeetthiscriteria, separation shallbemaintained asdescribed inSection8.2.2oftheGinnaFSAR.21.0FailureEffectsReuirements 21.1Thismodification shallbedesignedsuchthatafailureofaseparation group1component shallnotaffecttheoperability oftheseparation group2system.DesignCriteriaEWR1869Page7RevisionDa)e5580i2.90 P'I 21.221.322.022.1Theinstrumentation designated inthismodification asbeingineitherseparation group1or2shallbedesignedtowithstand theeffectsofasafeshutdownearthquake withnodegradation inperformance oraccuracy.

Thepressureandflowtransmitters installed intheIntermediate Buildingshallbedesignedtowithstand theenvironmental effectsofapostulated pipecrackwithnolossinperformance andaccuracy.

TestReirementsTestsshallbeperformed priortoplacingthismodifi-cationinservice, toensurethat,designrequirements havebeenmet.22.2Seismicqualification testingofsafetyrelatedinstru-mentation shallconformtotherequirements ofIEEE-323-1974andIEEE-344-1975.

22.3Environmental qualification testingofinstrumentation shallconformtotherequirements ofIEEE-323-1974, orIEEE-323-1971 asdescribed insection9.4.22.423.024.0Flametestingofcableutilizedinthismodification shallconformtotherequirements ofIEEE-383-1974.

Accessibilit

,Maintenance, ReairandInservice InsectionNone.Personnel Reirements25.026.0None.Transortabilit Reuirements None.FireProtection Reuirements 27.0Cableusedinthismodification shallmeettheflamespreadrequirements ofIEEE3831974.HandlinReuirements Electronic instrumentation shallbeshippedandstoredinaccordance withLevelBrequirements ofANSIN45.2.2.DesignCriteriaEWR1869Page8RevisionDate55804290 C~'aQl'~

28.029.0PublicSafetReuirements None.~11't.Materials andequipment utilizedinthismodification-shallbechosensuchthatthesedesignrequirements aremet.30.031.0Personnel Safet.Reuirements None.UniueReuirements None.DesignCriteriaEWR1869Page9RevisionDate5/5/804290 U1 CriAT%STCAIICCNCNATaAINSOCCONTANNltNT

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