Press Release-93-146, NRC Received from Advisory Committee on Reactor Safeguards Attached Report That Provides Comments on Proposed NRC Generic Letter Regarding Removal from Nuclear Power Plant Technical Specifications Accelerated Testing, Press Rele

Press Release-93-146, NRC Received from Advisory Committee on Reactor Safeguards Attached Report That Provides Comments on Proposed NRC Generic Letter Regarding Removal from Nuclear Power Plant Technical Specifications Accelerated Testing

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Press Release-93-146
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No.93-146October5,1993NOTETOEDITORS:TheNuclearRegulatoryCommissionhasreceivedfromitsAdvisoryCommitteeonReactorSafeguardstheattachedletter-typereportthatprovidescommentsonaproposedNRCgenericletterregardingremoval fromnuclearpowerplanttechnicalspecificationsacceleratedtestingandspecialreportingrequirements foremergencydieselgenerators.Inaddition,theACRShassenttwoletterreportstotheNRC'sExecutiveDirectorforOperations.Theyprovidecommentsonproposedpriorityrankingsofgenericissuesrelatedtonuclearfacilitiesand proposedrulesandadraftregulatoryguidethatdealwithlight-waterreactorpressurevesselissues.September22,1993TheHonorableIvanSelin,ChairmanU.S.NuclearRegulatoryCommission Washington,D.C.20555

SUBJECT:

PROPOSEDGENERICLETTERREGARDINGREMOVALOFACCELERATEDTESTINGANDSPECIALREPORTINGREQUIREMENTSFOREMERGENCYDIESELGENERATORSFROMPLANTTECHNICALSPECIFICATIONSDuringthe401stmeetingoftheAdvisoryCommitteeonReactorSafeguards,September9-10,1993,wereviewedthesubjectgenericletter(GL).Duringthismeeting,wehadthebenefitofdiscussionswithrepresentatives oftheNRCstaffandNUMARC.Wealsohadthebenefitofthedocumentsreferenced.ThestaffhasinformedusthatthisversionoftheproposedGLreflectsconsiderationofthecommentsmadebytheCommitteetoReviewGenericRequirements(CRGR).TheproposedGLhasbeenissuedforpubliccomment inaccordancewithouragreementthatthiscouldbedonepriortoourreview.TheproposedGLwouldallowlicenseestorequestremovaloftheTechnicalSpecification(TS)provisionsforacceleratedtestingandspecialreportingrequirementsfortheemergencydieselgenerators(EDGs).When requestingthislicenseamendment,licenseesmust,however,committoimplementamaintenanceprogramfor monitoringandmaintainingEDGperformanceconsistentwith10CFR50.65,"RequirementsforMonitoringthe EffectivenessofMaintenanceatNuclearPowerPlants,"andofRegulatoryGuide(RG)1.160,"Monitoringthe EffectivenessofMaintenanceatNuclearPowerPlants,"thatwasdevelopedbythestafftoprovideguidance forcomplyingwiththeprovisionsoftheMaintenanceRule,10CFR50.65.InourApril26,1993(revisedJune24,1993)reportonthedraftversionofRG1.160,wenotedthat:Onmanyoccasions,wehaveprovidedcommentsonthetrigger-valueapproachproposedbythestafftoresolveGenericIssueB-56,"DieselGeneratorReliability."Theproposedregulatoryguidefor implementingtheMaintenanceRuleexplicitlyendorsesthetrigger-valueprocedurefor"monitoring emergencydieselgenerator(EDG)performanceagainstEDGtargetreliabilitylevels."Itis categoricallyimpossibletodemonstratethereliabilityofEDGsusingthismethod.Weremain stronglyopposedtoitsuseforthispurposeandcontinuetorecommendthatthestaff's implementationguidancefortheStationBlackoutRule,10CFR50.63,berevisedtodealwiththis issue.Whenthisisdone,theregulatoryguideshouldbeappropriatelyrevised.Thestaff'sresponsewastoincludeafootnoteinRG1.160whichstates:Thetriggersareintendedtoindicatewhenemergencydieselgeneratorperformanceproblemsexistsuchthatadditionalmonitoringorcorrectiveactionisnecessary.Itisrecognizedthatitisnot practicaltodemonstratebystatisticalanalysisthatconformancetothetriggervalueswillensure theattainmentofhighreliability,withareasonabledegreeofconfidence,ofindividualEDGunits.Wedonotbelievethatthisfootnotesatisfactorilyresolvesourconcern.RegulatoryGuide1.160endorsesSection12.2.4ofNUMARC93-01,"IndustryGuidelinesforMonitoringtheEffectivenessofMaintenanceatNuclearPowerPlants,"which,inturn,referencesAppendixDofNUMARC87-00, Revision1,"GuidelinesandTechnicalBasesforNUMARCInitiativesAddressingStationBlackoutatLWRs."

Eachofthesedocumentsclearlyimpliesthatuseofthe"triggervaluesandmonitoringmethods"(asdescribed inAppendixDofNUMARC87-00,Revision1)providesanacceptablemeansofmonitoringEDGtarget reliabilitiesof0.95or0.975inaccordancewiththeintentof10CFR50.63forcopingwithstation blackouts.(See,forexample,thelanguageofthefirstparagraphoftheintroductiontoAppendixDof NUMARC87-00,Revision1.)Itcan'tbebothways!WestronglyrecommendthatthestaffandNUMARC collaborateinresolvingthismatterbyappropriaterevisionofthesedocuments.

WehavehadalongstandingconcernthattheEDGsatmanynuclearpowerplantsarebeingsubjectedtoexcessiveandunnecessarysurveillancetestingandothertestingasrequiredbyTSlimitingconditionsfor operation,andthatsuchtestingmayactuallybedegradingthereliabilityofthesemachines.Dataforthe years1988to1991,providedtousbyNUMARC,showthatsomeEDGsaresubjectedtostarttestingonly12to 15timeseachyear,whileotherEDGsaretestedover100timeseachyear.Thisdisparityintestingfrequenciesresults,inpart,fromthewidevariationinrelevantTSrequirementsthatwerenegotiatedwithlicenseesovertheyears.Thefactthatthissituationhasexistedforsomany yearsreflectsbadlyonboththestaffandlicenseeswithrespecttotheireffectivenessindealingwithan acknowledgedproblemhavingsafetyimplications.WebelievethatthisproposedGLisanimportantstepin achievingamorerationaltestingprogram.InadditiontoourrecommendationthatRG1.160andtheNUMARCdocumentsonwhichthisproposedGLisbasedberevisedtoreflectstatisticalreality,webelievethatthelanguageoftheproposedGLneedsimprovement.

TheproposedGLquotesastatementfromRG1

.160thattriggersandtestingof"problemdiesels"willbeaddressedseparatelybytheNRC.InthenextparagraphoftheGL,licenseecommitmentsrequiredforapproval oftheremovalofacceleratedtestingandspecialreportingrequirementsfromtheTSaredescribed,including theneedforacommitmenttoRG1.160.Astatementisthenmadethattheseactionsareintendedtoclose theissuesoftriggersandtestingfor"problemdiesels."Thestaffshouldclarifythisapparent contradictionandstateclearlythattheformerprescriptiverequirementforacceleratedtestinghasbeen eliminatedbythisproposedgenericletter.

Sincerely,J.ErnestWilkins,Jr.,ChairmanAdvisoryCommitteeonReactor Safeguards References

1.MemorandumdatedAugust13,1993,fromJ.Larkins,ACRS,toB.Grimes,OfficeofNuclearReactorRegulation,

Subject:

ProposedNRCGenericLetter"RemovalofAcceleratedTestingandSpecial ReportingRequirementsforEmergencyDieselGeneratorsfromPlantTechnicalSpecifications"2.MemorandumdatedAugust12,1993,fromG.Marcus,OfficeofNuclearReactorRegulation,forJ.Larkins,ACRS,forwardingproposedNRCGenericLetterRegardingRemovalofAcceleratedTestingand SpecialReportingRequirementsforEmergencyDieselGeneratorsfromPlantTechnicalSpecifications3.U.S.NRCRegulatoryGuide1.160,"MonitoringtheEffectivenessofMaintenanceatNuclearPowerPlants,"June19934.NUMARC93-01,"IndustryGuidelineforMonitoringtheEffectivenessofMaintenanceatNuclearPowerPlants,"May19935.AppendixD."EDGReliabilityProgram"toNUMARCReport,"GuidelinesandTechnicalBasesforNUMARCInitiativesAddressingStationBlackoutatLWRs,"NUMARC87-00,Revision1,August19916.SECY-93-044datedFebruary22,1993,fortheCommissionfromJamesM.Taylor,NRCExecutiveDirectorforOperations,

Subject:

ResolutionofGenericSafetyIssueB-56,"DieselGeneratorReliability"7.LetterdatedApril26,1993(RevisedJune24,1993),fromPaulShewmon,ACRSChairman,toBrianK.Grimes,OfficeofuclearReactorRegulation,

Subject:

ImplementationGuidancefortheMaintenance

Rule8.LetterdatedAugust7,1992,fromAlexMarion,NUMARC,toPaulBoehnert,ACRS,providingIndustrywideEmergencyDieselGeneratorReliabilityData9.LetterdatedDecember18,1992,fromRaymondFraley,ACRS,toAlexMarion,NUMARC,

Subject:

IndustrywideEmergencyDieselGeneratorReliabilityPerformanceData10.LetterdatedMarch1,1993,fromAlexMarion,NUMARC,toRaymondFraley,ACRS,respondingtoquestionsregardingIndustrywideEmergencyDieselGeneratorReliabilityPerformanceDataSeptember16,1993MEMORANDUMTO:JamesM.TaylorExecutiveDirectorforOperationsFROM:J.ErnestWilkins,Jr.Chairman,ACRS

SUBJECT:

PROPOSEDPRIORITYRANKINGSOFGENERICISSUES:EIGHTHGROUP Duringthe401stmeetingoftheAdvisoryCommitteeonReactorSafeguards,September9-10,1993,wereviewedthepriorityrankingsproposedbytheNRCstaffforthegenericissueslistedintheattachedtable.During thismeeting,wehadthebenefitofdiscussionswithrepresentativesoftheNRCstaff.Weagreewithalloftheproposedpriorityrankings.Wenote,however,thatthesafetyconcernsofseveralgenericissuesaretobeevaluatedandresolvedthroughtheIndividualPlantExamination(IPE)andIndividual PlantExaminationofExternalEvents(IPEEE)processes,oraretobetreatedaslicensingissues,ortobe handledinsomeothermanner.Wearenotsurewhetherthelargenumberoflicenseeswhohavealready completedtheirIPEshaveevaluatedtheseissues.Webelievethatthestaff,whilereviewingtheIPEand IPEEEsubmittals,shouldensurethatthesegenericissueshavebeenevaluatedandresolvedbythelicensees inanadequatemanner.IntheeventsomeofthelicenseeshadnotconsideredtheseissuesintheirIPEsor IPEEEs,thestaffshouldestablishamechanismtorequirethemtoevaluatetheseissues.Thestaffshould alsoestablishasystemtokeeptrackoftheresolutionofalloftheissuesthathavebeenincludedinother programsforresolution.Wewouldliketohearareportfromthestaff,atanappropriatetime,ontheadequacyofresolutionofallthesegenericissues.

J.ErnestWilkins,Jr.,ChairmanAdvisoryCommitteeonReactor Safeguards

Attachment:

Asstated September20,1993Mr.JamesM.TaylorExecutiveDirectorforOperations U.S.NuclearRegulatoryCommission Washington,D.C.20555

SUBJECT:

PROPOSEDRULEAMENDINGFRACTURETOUGHNESSREQUIREMENTSFORLIGHTWATERREACTORPRESSUREVESSELS,PROPOSEDRULEREGARDINGREQUIREMENTSFORTHERMALANNEALINGOFREACTORPRESSUREVESSELS,ANDDRAFTREGULATORY GUIDEONFORMATANDCONTENTOFAPPLICATIONFORAPPROVALFORTHERMALANNEALINGOFREACTORPRESSUREVESSELSDuringthe401stmeetingoftheAdvisoryCommitteeonReactorSafeguards,September9-10,1993,wediscussedthesubjectproposedrulesanddraftregulatoryguide.OurSubcommitteeonMaterialsandMetallurgyreviewed thesemattersindetailatameetingonAugust16,1993.Duringthesemeetings,wehadthebenefitof discussionswithrepresentativesoftheNRCstaff.Wealsohadthebenefitofthedocumentreferenced.Theneedfortheseproposedrulesandthedraftguidewas,inpart,highlightedduringtheevaluationoftheintegrityoftheYankeeNuclearPowerStation'sreactorpressurevessel.Webelievetheserulesandthis guideshouldproveusefultothelicenseesandtheNRCstaffandrecommendthattheybeissuedforpublic comment.Wewouldlikeanopportunitytoreviewtheproposedfinalversionoftheserulesandguideafter thepubliccommentshavebeenreconciledandbeforepublication.AdditionalcommentsbyACRSMembersIvanCattonandWilliamJ.Lindbladarepresentedbelow.

Sincerely,J.ErnestWilkins,Jr.,ChairmanAdvisoryCommitteeonReactorSafeguardsAdditionalCommentsByACRSMembersIvanCattonandWilliamJ.LindbladAlthoughweagreewiththeessenceoftheaboveletter,weopposetheeliminationoftheprovisioninAppendixHwhichcurrentlypermitsareductionoftestinginIntegratedSurveillanceProgramswhere"initial resultsagreewithpredictions."Thelicensee'sprogramis,afterall,subjecttostaffapprovalona"case-by-casebasis."Licenseesshouldhavesomeflexibilityinschedulingwhentheyactuallytestspecimens.

Thisdoesnotmeanthatspecimenswouldnotbeirradiated.

Reference:

MemorandumdatedAugust20,1993,fromAllenL.Hiser,Jr.,OfficeofNuclearRegulatoryResearch,forElpidioG.Igne,ACRS,

Subject:

ResponsetoRequestatACRSSubcommitteeMeeting,withthefollowing:a.FederalRegisterNoticeforProposedRule,10CFRPart50,"FractureToughnessRequirementsforLightWaterReactorPressureVessels"b.Aproposedrule(10CFR50.66)onthermalannealingofthereactorpressurevessel,"RequirementsforThermalAnnealingoftheReactorPressureVessel"c.Amendmentsto10CFRPart50AppendixG,"FractureToughnessRequirements" d.Amendmentsto10CFRPart50AppendixH,"ReactorVesselMaterialSurveillanceProgramRequirements" e.Adraftregulatoryguide(DG-1027),"FormatandContentofApplicationforApprovalforThermalAnnealingofReactorPressureVessels"