ML17263A641

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Application for Amend to License DPR-18,revising TS Administrative Controls Section 6.0 Consistent W/Improved TS
ML17263A641
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/13/1994
From: MECREDY R C
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A642 List:
References
NUDOCS 9405170066
Download: ML17263A641 (36)
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UNITEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSIONIntheMatterof))RochesterGasandElectricCorporation)(R.E.GinnaNuclearPowerPlant))DocketNo.50-244APPLICATIONFORAMENDMENTTOOPERATINGLICENSEANDUALITYASSURANCEPROGRAMPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(NRC),RochesterGasandElectricCorporation(RGEE),holderofFacilityOperatingLicenseNo.DPR-18,herebyrequeststhattheTechnicalSpecificationssetforthinAppendixAtothatlicensebeamended.ThisrequestforchangeinTechnicalSpecificationsistorevisetheAdministrativeControlsesectionconsistentwithImprovedTechnicalSpecifications.SeveralrequirementsarealsorelocatedtootherprogramsanddocumentsinaccordancewiththecriteriacontainedintheNRCFinalPolicyStatementonTechnicalSpecificationsImprovementsforNuclearPowerReactors.Adescriptionoftheamendmentrequest,necessarybackgroundinformation,justificationoftherequestedchange,safetyevaluationandnosignificanthazardsandenvironmentalconsiderationsareprovidedinAttachmentA.Thisevaluationdemonstratesthattheproposedchangesdonotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeffluentsoranychangeintheauthorizedpowerlevelofthefacility.Theproposedchangesalsodonotinvolveasignificanthazardsconsideration.9405i70066'v4()gag.T()PDR-ADOCK,05000244,f~P.,PDP J

AmarkedupcopyofthecurrentGinnaStationTechnicalSpecificationswhichshowtherequestedchangesissetforthinAttachmentB.TheproposedrevisedTechnicalSpecificationsareprovidedinAttachmentC.AmarkedupcopyofStandardTechnicalSpecificationsisprovidedinAttachmentDwhichshowsallapplicablechanges.WHEREFORE,ApplicantrespectfullyrequeststhatAppendixAtoFacilityOperatingLicenseNo.DPR-18beamendedintheformattachedheretoasAttachmentC.RochesterGasandElectricCorporationByRbertC.HecredyVicePresidentNuclearProductionSubscribedandsworntobeforemeonthis13thdayofHay1994.NotaryPublic

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AttachmentAR.E.GinnaNuclearPowerPlantLicenseAmendmentRequestUpgradeofAdministrativeControlsTechnicalSpecification6.0Thisattachmentprovidesadescriptionoftheamendmentrequestandnecessaryjustificationfortheproposedchanges.Theattachmentisdividedintosevensectionsasfollows.SectionAidentifiesallchangestothecurrentGinnaStationTechnicalSpecificationswhileSectionBprovidesthebackgroundandhistoryassociatedwiththechangesbeingrequested.SectionCprovidesdetailedjustificationfortheproposedchangesincludingacomparisontoImprovedTechnicalSpecificationsasapplicable.Asafetyevaluation,significanthazardsconsiderationevaluation,andenvironmentalconsiderationoftherequestedchangesareprovidedinSectionsD,E,andF,respectively.SectionGlistsallreferencesusedinthisattachment.'.DESCRIPTIONOFAMENDMENTREQUESTThisLicenseAmendmentRequest(LAR)proposestoreviseGinnaStationTechnicalSpecification(TS)6.0assummarizedbelow.AttachmentBcontainsamarkedupcopyofthecurrentGinnaStationTechnicalSpecificationsshowingtherequestedchanges.TheTechnicalSpecificationsfollowingtheproposedchangesisprovidedinAttachmentC.Notethatformatissuesandminorwordingchangesareexcludedfromthediscussionbelow:2.3.5.TechnicalSpecificationTableofContentsi.Revisedtosupportproposedchanges.TechnicalSpecification3.1.4.3.ai.DeletedspecialreportrelatedtoexceedingI-131equivalentactivitylimits.TechnicalSpecification3.5.5.3Deleted"Semiannual"fromthenameoftheRadioactiveEffluentReleaseReport.TechnicalSpecification3.6RevisedbasestoreplacereferencetoTS6.8withtheQualityAssuranceProgram.TechnicalSpecification3.15.1.3i.Revisedreferencetospecialreporttechnicalspecificationsection.

TechnicalSpecification3.16.1TS3.16.1.3isrevisedtoreplacereferencestoTable6.9.2withtheOffsiteDoseCalculationHanual(ODCH).TS3.16.1.4isrevisedtodelete"Semiannual"andadd"Release"tothenameoftheRadioactiveEffluentReleaseReport.TechnicalSpecification6.1TS6.1.1isrevisedtoincludeastatementthatthePlantHanagershallapproveeachproposedtest,experimentormodificationtostructures,systemsorcomponentsthataffectnuclearsafety.Addedanewrequirement(TS6.1.2)whichoutlinestheShiftSupervisor's(SS)responsibilitiesandwhocanbedesignatedtoassumethecontrolroomcommandfunctionwhentheSSisabsent.TechnicalSpecification6.2TS6.2.l.aisrevisedtoincludearequirementforfunctionaldescriptions'fdepartmentalresponsibilitiesandrelationshipsandjobdescriptionsofkeypersonnelpositions.TS6.2.1.b,6.2.1.c,6.2.2.a,6.2.2.b,6.2.2.c,6.2.2.d,6.2.2.fandTable6.2-1aredeleted.V.Vl.TS6.2.2.aisreplacedwithastatementdefiningwhennon-licensedoperatorsarerequiredtobeassignedtotheshiftcrew.ThisrequirementcurrentlyexistsinTable6.2-1.TS6.2.2.bisreplacedwithastatementdefiningtheconditionsanddurationsthatoperatingshiftcrewcompositionsmaybelessthanthatspecifiedin10CFR50.54(k),(l),and(m),andintheTechnicalSpecifications.ThisstatementcurrentlyexistsinTable6.2-1.TS6.2.2.eisrenumberedandrevisedtoallowtheindividualqualifiedinradiationprotectionprocedurestobeabsentfornotmorethan2hours.TS6.2.2.gisrenumberedandrevisedtoreferenceaNRCapprovedprogramforcontrollingovertime.viii.Addedanewrequirement(newTS6.2.2.e)whichdefinestheresponsibilitiesandqualificationsofthe'ShiftTechnicalAdvisor(STA).

l,y 9.TechnicalSpecification6.3i.TS6.3.1isrevisedtodeletereferencetotheSTAfunctionandstandardizethereferencetoRegulatoryGuide1.8.10.TechnicalSpecification6.4i.Deletedentiresection.ll.TechnicalSpecification6.5i.Deletedentiresection.'2.TechnicalSpecification6.6i.Deletedentiresection.13.TechnicalSpecification6.7i.TSSectionisnow6.8.ii.TS6.7.aisrevisedtoupdatereferenceto10CFR5036(c)(1)(i)(A)iii.TS6.7.band6.7.darerevisedtoreplacethereferenceto.NSARBwith"offsitereviewfunction"andSeniorVicePresident,ProductionandEngineering,with"corporateexecutiveresponsibleforoverallplantnuclearsafety."iv.TS6.7.cisrevisedtoreplacereferencetoPORCwith"onsitereviewfunction."14.TechnicalSpecification6.8i.TSSectionisnow6.4.ii.TS6.8.l.aisrevisedtoreferenceRevision2ofRegulatoryGuide1.33,AppendixA,insteadofRevision0.iii.TS6.8.l.b,6.8.l.c,6.8.1.d,6.8.l.e,6.8.l.f,6.8.1.g,6.8.l.h,6.8.l.i,6.8.2,and6.8.3aredeleted.iv.TS6.4.l.bisaddedwhichrequireswrittenemergencyoperatingprocedureswhichimplementtherequirementsofNUREG-0737andNUREG-0737,Supplement1.v.TS6.4.l.cisaddedwhichrequireswrittenproceduresforallprogramsspecifiedinnewTS6.5.15.TechnicalSpecification6.9i.TSSectionisnow6.6.

ii.TS6.9.1.1,6.9.1.5,6.9.2.1,6.9.2.3,6.9.2.4,6.9.2.5,andTable6.9-2aredeleted.iii.TS6.9.1.2isrevisedtorequiredocumentationofallchallengestothepressurizerpoweroperatedreliefvalvesorthepressurizersafetyvalves.iv.TS6.9.1.3isrevisedtodeletealldiscussionrelatedtoformatandcontentoftheAnnualRadiologicalEnvironmentalReportincludingdeletionofTable6.9-1.Referencesto10CFR50,AppendixI,SectionsIV.B.2,IV.B.3,andIV.CareaddedandthesubmittaldateischangedfromHay1stofeachyeartoNay15th.V.TS6.9.1.4isrevisedtodeletealldiscussionrelatedtoformatandcontentoftheRadiologicalEffluentReleaseReport.Referencesto10CFR50.36aand10CFR50,AppendixI,SectionsIV.B.1areaddedandthesemiannualsubmittalrequirementischangedtoanannualreport.vi.TS6.9.2.2isrevisedtoupdatethereferencesto10CFR20andspecifyarequiredsubmittaldate.16.TechnicalSpecification6.10i.Deletedentiresection.17.TechnicalSpecification6.11i.Deletedentiresection.18.TechnicalSpecification6.12i.Removedpreviouslydeletedsection.19.TechnicalSpecification6.13i.TSSectionisnow6.7.ii.Revisedentiresectionconsistentwithnew10CFR20.20.TechnicalSpecification6.14i.Removedpreviouslydeletedsection.21.TechnicalSpecification6.15SignificantlyrevisedentiresectionandmovedtheOffsiteDoseCalculationHanualtonewTS6.5.1.22.TechnicalSpecification6.16i.Deletedentiresection. 23.TechnicalSpecification6.17i.Deletedentiresection.24.NewTechnicalSpecificationSection6.5i.AddednewTS6.5.1whichdefinestheOffsiteDoseCalculationManual.ii.AddednewTS6.5.2whichdefinesthePostAccidentSamplingProgram.BACKGROUND1.HistoryOnFebruary6,1987,theNRCissuedaninterimPolicyStatementonTechnicalSpecificationImprovementsforNuclearPowerReactorswhichproposedcriteriafordefiningthescopeofwhatshouldbecontainedwithintechnicalspecifications.ThesecriteriaweredevelopedasaresultofeffortswithintheNRCandnuclearindustrytorelocatemanyexistingrequirementstoothermoreappropriateprogramsanddocumentsinordertostreamlinethetechnicalspecifications.Therelocatedrequirementswouldthenbecontrolledbyotherexistingregulations(e.g.,10CFR50.59).Thisrelocationwouldresultinmoreconcisetechnicalspecificationswhichfocusedonthemostimportantrequirementswithoutanyreductioninsafety.FollowingissuanceoftheinterimPolicyStatement,theNRCandnuclearindustrybegandevelopmentofnewstandard(orimproved)technicalspecificationswhichimplementedtheproposedcriteria,providedgreateremphasisonhumanfactorsprinciples,andcontaineddetailedbasesforeachretainedspecification.TheendproductofthiseffortwasthereleaseoffiveNUREGsinSeptember1992whichcontainedtheImprovedTechnicalSpecifications(ITS)foreachofthefourNSSSvendors(twoNUREGswereissuedforBWRs).TheseNUREGscontainedalloftheimprovementsdiscussedaboveandalsoso-called"line-item"improvementswhicharegenericrefinementstothetechnicalspecificationsthatwereidentifiedsubsequenttotheinterimPolicyStatement.TheNUREGswerethenfollowedbyafinalPolicyStatementwhichbecameeffectiveonJuly22,1993,andencouragedlicenseestoimplementtheITS.InresponsetothereleaseoftheITSandthecontinuedpublicationofnew"line-item"improvements,RGEEbeganconsiderationofimplementingNUREG-1431(Reference1)whichcontainedthenewtechnicalspecificationsforWestinghouseplants.FollowingdiscussionswiththeNRCstaff,RGLEdecidedtoinitiateaTechnicalSpecificationImprovementProgram(TSIP)andimplementtheITSforGinnaStation(Reference2).ThisprogramwillconsistofrelocatingcurrentrequirementsinaccordancewiththefinalPolicyStatementonTechnicalSpecificationsandreformattingtheremainingrequirementsconsistentwithNUREG-1431.Ingeneral,newrequirementscontainedinNUREG-1431thatarenotinthecurrentGinnaStationTechnicalSpecificationswillnotbeadded.

IIsa BasedondiscussionswiththeNRCstaff,thefirststepintheTSIPisconversionoftheAdministrativeControlssectionoftechnicalspecifications.ThissectionwasselectedsinceRG&EpreviouslysubmittedaLARrelatedtothePlantOperationsReviewCommittee(PORC)membershiprequirementswhicharecontainedintheAdministrativeControlssection(Reference3).ThatLARhasnotbeenapprovedbytheNRCandissupersededbythissubmittal.Theremainingsectionsoftechnicalspecificationswillbeconvertedatalaterdate.SubsequenttotheissuanceoftheNUREGs,theNRCproposedthatthecontentoftheITSAdministrativeControlssectionbesignificantlyreducedtoeliminateduplicationwithotherregulatoryrequirements(Reference4).ThenuclearindustryevaluatedtheproposedchangesandformallysubmittedrevisionstotheITSAdministrativeControlssectionbasedontheinformationprovidedbytheNRCandadditionalresearchandstudy(Reference5).RG&EhasevaluatedthenuclearindustryproposedchangesanddecidedtosubmitaLARwhichimplementstheITSformatfortheAdministrativeControlssection(GinnaStationTechnicalSpecificationSection6)andrelocatesrequirementsconsistentwithReference5.AdministrativecontrolsthatarecontainedinNUREG-1431whicharerelatedtorequirementsthatwillbeaddressedduringtheconversionoftheremainingGinnaStationTechnicalSpecificationsarenotincludedwiththisLAR.ExamplesofrequirementswhicharenotaddedatthistimeincludetheSafetyFunctionDetermination,ExplosiveGasandStorageTankRadioactivityMonitoring,andtheBasesControlPrograms.Inaddition,acurrentrequirementforaddressingSafetyLimitViolationsisretainedwithintheAdministrativeControlssectioninordertopreventtheneedtoreviseadditionalTechnicalSpecificationsections.TheSafetyLimitViolationrequirementwillberelocatedtoGinnaStationTechnicalSpecificationSection2duringtheconversionoftheremainingsections.2.HardwareModificationsTherearenoplantmodificationswhicharerequiredtoimplementthechangesrequestedinthisLAR.Section6oftheTechnicalSpecificationsaddressestheadministrativecontrolswhichareinplacetoassurethatGinnaStationisoperatedinasafemanner.Thesecontrolstypicallyconsistofprogramsandperiodicreportingrequirements.Revisingthecurrentadministrativecontrols,removingcurrentcontrolswhichduplicaterequirementscontainedwithintheCodeofFederalRegulations,orrelocatingcontrolstootherprogramsdoesnotrequireanyplantmodifications.Anychangestoplantprocedures,theUpdatedFinalSafetyAnalysisReport(UFSAR),orthegAProgramwhicharenecessarytosupportthechangesrequestedbythisLARwillalsonotresultinanyplantmodifications. C.JUSTIFICATIONReformattingthecurrentAdministrativeControlssectionwillprovideasignificanthumanfactorsimprovementbylocatingsimilarrequirements,-,withinthesamesectionandprovideastandardstructure.ThereareseveraltypesofchangesthatarebeingrequestedbythisLARinordertoperformthereformatting.Thetechnicalandsignificantadministrativechanges,andthebasisforthesechanges,aresummarizedbelow.SincetheupgradeoftheAdministrativeControlssectionisbeingperformedconsistentwiththeITS,amarkedupcopyofSection5.0ofNUREG-1431isprovidedinAttachmentD.ThisattachmentshowsallproposedchangeswithrespecttoITSforWestinghouseplants.AcrossreferenceisprovidedintheleftmarginofeachITSspecificationthathasbeenchangedbyuseofacirclecontainingsectionnumbersfrombelow.RequirementscontainedwithinthecurrentGinnaStationTechnicalSpecificationsareidentifiedas"TS";withintheproposedfinalGinnaStationTechnicalSpecifications(i.e.,AttachmentC)as"newTS";andwithinNUREG-1431as"ITS."RelocationofRequirementsWithinTechnicalSpecificationSection6Manycurrentrequirementsaremovedtosupportconsolidationofsimilaradministrativecontrolswithinthesamesection.Sincetherequirementsareonlybeingrelocatedwithinthetechnicalspecifications,thereisnoreductioninsafety.ThefollowingGinnaStationrequirementswererelocatedwithintheAdministrativeControlsSection6:TS6.2.l.c-theresponsibilitiesofthePlantManageraredeletedsincethisisaddressedbynewTS6.1.1.TS6.3.1-thecurrentrequirementsforShiftTechnicalAdvisors(STAs)aremovedtonewTS6.2.2.e.ThereferencetotheRGKEletterdatedDecember30,1980,wasreplacedwithastatementrequiringtheSTAsto"meetthequalificationsspecifiedwithinaNRCapprovedSTAtrainingprogram."ThischangeisdifferentthanthewordingcontainedinNUREG-1431whichrequirestheSTAtomeet,thequalificationsspecifiedintheCommissionPolicyStatementonEngineeringExpertiseonShift(i.e.,GenericLetter86-04).ThecurrentSTAprogramatGinnaStationisdiscussedinReferences6and7andhasbeenreviewedandapprovedbytheNRC.SincetheSTAprogramdoesnotmeetalltherequirementscontainedwithinGL86-04,theproposedwordingisconsideredmoreappropriateandconsistentwiththecurrenttechnicalspecifications.ThedeletionofthespecificreferencetoanRG&ElettereliminatestheneedtorevisetechnicalspecificationsiftheSTAprogramislaterrevised.

Jf,ikt iii.TS6.4-therequirementsforaTrainingProgramaredeletedsinceTS6.3specifiesthatallmembersoftheGinnaStationstaffmustmeetorexceedtheminimumrequirementsofANSIStandardN18.1-1971.ThisANSIStandardrequiresaretrainingandreplacementtrainingprogramwhichensures"safeandefficientoperationofthefacility."Requirementsforlicensedoperatortrainingareaddressedby10CFR55.TS6.8.l.b,6.8.l.c,and6.8.l.f-therequirementsforwrittenprocedureswhichaddressrefuelingoperations,surveillanceandtestactivitiesofsafetyrelatedequipment,andFireProtectionprogramimplementationaredeletedsincethesearespecifiedinRegulatoryGuide1.33,AppendixA,Revision2(newTS6.4.l.a).V.TS6.8.l.g-therequirementforwrittenproceduresfortheradiologicalenvironmentalmonitoringprogramisdeletedsincethisisaddressedinthespecificationfortheOffsiteDoseCalculationHanual(newTS6.5.1).TheOffsiteDoseCalculationHanualisrequiredtocontain"themethodologyandparametersusedin...theconductoftheradiologicalenvironmentalmonitoringprogram."vi.TS6.8.l.h-therequirementforwrittenproceduresfortheOffsiteDoseCalculationHanualismovedtonewTS6.5.1.TS6.9.1.5and6.9.2.4-therequirementforreportingpressurizerpoweroperatedreliefvalveandpressurizersafetyvalvechallengesismovedtotheHonthlyOperatingReportSpecification(newTS6.6.4).viii.TS6.15-theOffsiteDoseCalculationHanualisrevisedconsistentwithNUREG-1431andITSTravellerBWOG-09andmovedtonewTS6.5.1.EliminationofDuplicatedRegulatoryRequirementsSeveraladministrativecontrolscurrentlyduplicateotherregulatoryrequirements.Theremovalofthesetypeofadministrativecontrolseliminatestheneedtochangetechnicalspecificationswhentherearerulechanges.Asanexample,therecentrevisionsto10CFR20willrequireRG3Etorevisethetechnicalspecifications.SincealllicenseesmustmeettheapplicablerequirementscontainedintheCodeofFederalRegulations,orhaveNRCapprovedexemptions,therearesufficientregulatorycontrolsinplacetoalloweliminationofduplicatedrequirementsfromtechnicalspecifications.Theimplementationoftheserequirementsarecontainedinproceduresandotherlicenseecontrolleddocuments.ThefollowingrequirementswereremovedfromtheAdministrativeControlsSection6(orrevisedasnoted)sincetheyduplicateexistingregulatoryrequirements:

TS3.1.4.3.aand6.9.2.3-reportingrequirementsforexceedingtheprimarycoolantspecificactivitylimitslistedinTS3.1.4.l.aand3.1.4.l.barespecifiedin10CFR50.73(2)(i)(A).TS6.2.2.a,6.2.2.b,6.2.2.c,6.2.2.d,andTable6.2-1requiredoperatingcrewcompositionsarespecifiedin10CFR50.54(k),(l),and(m)andnewTS6.2.2.a,6.2.2.b,and6.2.2.e.TS6.6-requirementsforreportableeventsarespecifiedin10CFR50.72,10CFR50.73,andotherregulations.TS6.8.l.d-therequirementforwrittenprocedureswhichimplementtheSecurityPlanarespecifiedin10CFR50.54(p)(l)and10CFR73.55(b)(3).EliminationofthisrequirementisconsistentwithGenericLetter93-07(Reference8).TS6.8.l.e-therequirementforwrittenprocedureswhichimplementtheEmergencyPlanarespecifiedin10CFR50.54(q)and50.54(t),and10CFR50,AppendixE,SectionV.EliminationofthisrequirementisconsistentwithGenericLetter93-07(Reference8).TS6.9.1.3andTable6.9-1-theformatandcontentoftheAnnualRadiologicalEnvironmentalReportiscontainedintheOffsiteDoseCalculationHanualspecification(newTS6.5.1)andthereferencedRadiologicalAssessmentBranchTechnicalPosition,Revision1,November1979.Referencesto10CFR50,AppendixI,SectionsIV.B.2,IV.B.3,andIV.CwereaddedtosupportdeletionofthereportformatandcontentandthesubmittaldatewaschangedfromHay1stofeachyeartoHay15thconsistentwithNUREG-1431.TS6.9.1.4-theformatandcontentoftheRadiological'.EffluentReleaseReportiscontainedinOffsiteDoseCalculationHanualspecification(newTS6.5.1).Referencesto10CFR50.36aand10CFR50,AppendixI,SectionIV.B.1wereaddedconsistentwithNUREG-1431.Thesemiannualsubmittalrequirementisalsochangedtoanannualreportinaccordancewith10CFR50.36a(a)(2).TS6.9.2.1-reportingrequirementsrelatedtosealedsourcesarespecifiedin10CFR30.50.TS6.9.2.5-licenseesubmittalsareaddressedby10CFR50.4.TS6.11-therequirementforaRadiationProtectionProgramisspecifiedin10CFR20.1101.

Ey~I'\ xi.TS6.17-changestotheRadioactiveWasteTreatmentsystemsarecontrolledby10CFR50.59.NRCnotificationofsignificantchangestothesesystemsisaddressedby10CFR50.59(b)(2).3.RelocationofCurrentAdministrativeControlRequirementsToOtherControlledDocumentsTherelocationofcertainrequirementscontainedintheAdministrativeControlssectiontootherlicenseecontrolleddocuments(i.e.,gAProgramandplantprocedures),doesnoteliminatetheprogram.Instead,therequirementsarerelocatedtoothermoreappropriatedocumentsandprogramswhichhavesufficientcontrolsinplacetomanageimplementationandfuturechanges(e.g.,10CFR50.54(a)(3)and10CFR50.59).TherelocationoftheseitemswillenableRGKEtomoreefficientlymaintaintherequirementsunderexistingregulationsandreducetheneedtorequesttechnicalspecificationchangesforissueswhichdonotaffectpublicsafety.ThefollowingsectionswererelocatedfromtheAdministrativeControlsSection6tothegAProgramorplantprocedures:TS3.16.1.3andTable6.9-2-ReportinglevelsforradioactivityconcentrationsinenvironmentalsampleswillbeaddressedinandimplementedbyprocedureRD-15.0,OffsiteDoseCalculationHanual(Reference9).RelocatingthereportinglevelstotheOffsiteDoseCalculationManualisconsistentwiththerequiredcontentofthismanualasspecifiedinnewTS6.5.1.ChangestotheOffsiteDoseCalculationHanualisalsoaddressedbynewTS6.5.1whichprovidessufficientcontrolwithrespecttomaintainingappropriatereportinglevelsforradioactivityconcentrations.TS6.2.1.b,6.7.band6.7.d-theresponsibilitiesoftheSeniorVicePresident,ProductionandEngineering.NewTS6.2.I.arequiresthat"linesofauthority,responsibilityandcommunicationshallbeestablishedanddefinedthroughoutthehighestmanagementlevels."SpecifyingmanagementpositionsbytitlewithinthetechnicalspecificationscreatesalicenseeandNRCburdenwhentitlesarechangedorresponsibilitiesareshifted.TheresponsibilitiesofkeyorganizationpositionsarespecifiedintheGinnaStationgAProgram.SincechangestothegAProgramarecontrolledby10CFR50.54(a)(3),equivalentcontrolisprovided.TS6.2.1;d-thecapabilityoftraining,healthphysicsandqualityassurancetohavedirectaccesstoresponsiblecorporatemanagementtosupportmitigationoftheirconcerns.NewTS6.2.l.arequiresthat"linesofauthority,responsibilityandcommunicationshallbeestablishedanddefinedthroughoutthehighestmanagementlevels."TheorganizationalstructureisspecifiedintheGinnaStationgAProgram.SincechangestothegAProgramarecontrolledby10CFR50.54(a)(3),equivalentcontrolisprovided. 1V~TS6.5,6.6.l.b,6.7.b,6.7.cand6.7.d-theReviewandAuditfunctions,includingthecompositions,meetingfrequencies,andresponsibilitiesofthePORC,NSARBandgA.ThenecessarychangestothegAProgramtosupportrelocationarebeingrequestedseparately.ChangestothegAProgramarecontrolledby10CFR50.54(a)(3)whichprovidesequivalentcontrol.v.V1~TS6.8.l.iand6.16-TheProcessControlProgramisaddressedinandimplementedbyprocedureRD-16.0,ProcessControlProgram(Reference10).Thisprogramensurescompliancewith10CFR20,10CFR61,and10CFR71whichregulatetheprocessingandpackagingofsolidradioactivewastes.ThefailuretomeettheseregulationsissufficientlyaddressedwithintheCodeofFederalRegulations.SincetheProcessControlProgramonlyensurescompliancewithexistingregulations,itisacceptabletorelocatethisprogramtoplantprocedureswhichareunderthecontrolof10CFR50.59.TS6.8.2and6.8.3andBasesforTS3.6-controlofchangestowrittenproceduresandtheuseandapprovaloftemporaryprocedurechanges.ThenecessarychangestothegAProgramtosupportrelocationarebeingrequestedseparately.ChangestothegAProgramarecontrolledby10CFR50.54(a)(3)whichprovidesequivalentcontrol.TS6.10-RecordRetentionrequirements.ThesearecurrentlyspecifiedinthegAProgram.ChangestothegAProgramarecontrolledby10CFR50.54(a)(3)whichprovidesequivalentcontrol.AdditionofNewITSAdministrativeControlRequirementsThereareseveralrequirementscontainedinNUREG-1431whicharenotcurrentlyintheGinnaStationTechnicalSpecifications.ThefollowingNUREG-1431(ITS)requirementswereaddedtothecurrentGinnaStationAdministrativeControlssectioninordertoprovideamorecompletespecification:ITS5.1.1(TS6.1.1)-PlantManagerresponsibilitiesrelatedtoapprovingeachproposedtest,experimentormodificationstosystems,structuresorcomponentsthataffectnuclearsafety.ITS5.1.2(TS6.1.2)-ShiftSupervisorresponsibilitiesandallowedabsencesfromthecontrolroom.1V.ITS5.2.l.a(TS6.2.l.a)-arequirementfor,functionaldescriptionsofdepartmentalresponsibilitiesandrelationshipsandjobdescriptionsofkeypersonnelpositions.ITS5.2.l.c(TS6.2.2.e)-allowstheindividualqualifiedinradiationprotectionprocedurestobeabsentfornotmorethan2hours.

'III v.ITS5.7.l.l.a(TS6.4.l.a)-requireswrittenproceduresinaccordancewithRevision2ofRegulatoryGuide1.33,AppendixA,insteadofthecurrentreferencetoRevision0.vi.ITS5.7.l.l.b(TS6.4.l.b)-requireswrittenemergencyoperatingprocedureswhichimplementtherequirementsofNUREG-0737andNUREG-0737,Supplementl.vii.ITS5.7.l.l.g(TS6.4.l.c)-requireswrittenproceduresforallprogramsspecifiedinTS6.5.rviii.ITS5.7.2.6(TS6.5.2)-requiresaPostAccidentSamplingPro'gram.ITSAdministrativeControlsDeferredUntilConversionofRemainingTSSectionsSeveralITSAdministrativeControlrequirementswerenotaddedsincetheywillbeaddressedduringtheconversionof.theremainingtechnicalspecificationssections.TheiradditionisdelayedsincetheyarecurrentlyaddressedelsewherewithintheGinnaStationTechnicalSpecificationsoraredirectlyrelatedtotheconversionoftheremainingsections.ThefollowingNUREG-1431administrativecontrolrequirements(orissues)willbeevaluatedduringtheconversionoftheremainingchapters:TheuseofModes1through6.ThiswasreplacedwiththecurrentnomenclatureofRefueling,'oldShutdown,HotShutdown,andOperating(seeTS1.2).ThenumberingoftheAdministrativeControlssectionremains6.0(versus5.0)untiltheconsolidationofTechnicalSpecificationsSections3.0and4.0.ill~1V.ITS5.6,TechnicalSpecificationsBasesControl-thisprogramwillbeimplementedfollowingconversionoftheremainingchapters.ITS5.7.1.1.e,gualityAssuranceforEffluentandEnvironmentalMonitoring-therequirementsforeffluentandenvironmentalmonitoringareaddressedbyTS3.16,RadiologicalEnvironmentalMonitoring,andTS4.10,RadiologicalEnvironmentalMonitoringSurveillances.TheGinnaStationTechnicalSpecificationscurrentlyrequire(andthegAProgramwillrequire)independentauditsatleastonceperyeartoensure"theconformanceoffacilityoperationtoallprovisionscontainedwithinTechnicalSpecifications."Therefore,sufficientqualityassuranceoftheseactivitiesexists.v~"ITS5.7.2.4,PrimaryCoolantSourcesOutsideContainment-thecontrolofleakagefromsystemsthatcouldcontainhighlyradioactivefluidsandwhichexitcontainmentisaddressedbyTS4.4.3,RecirculationHeatRemovalSystems. V1.V11.ITS5.7.2.5,InPlantRadiationMonitoringProgram-thecapabilitytodetermineairborneiodineconcentrationsinvitalareasunderaccidentconditionsisaddressedbyTS3.5.4andTable4.1-5.ITS5.7.2.7,RadioactiveEffluentControlsProgram-therequirementtoprovidelimitationsonliquidandgaseousreleasesisaddressedbyTS3.9,PlantEffluents,andTS4.12,EffluentSurveillance.V111~1X.ITS5.7.2.8,RadiologicalEnvironmentalMonitoringProgram-therequirementtomonitor,sample,andreportradiationandradionuclidesintheenvironmentisaddressedbyTS3.16,RadiologicalEnvironmentalMonitoring,andTS4.10,RadiologicalEnvironmentalMonitoringSurveillances.ITS5.7.2.10,Pre-StressedConcreteContainmentTendonSurveillanceProgramandITS5.9.2.d,SpecialReportrelatedtoabnormaldegradationobservedbythePre-StressedContainmentTendonSurveillanceProgram-requirementsrelatedtocontainmenttendondegradationareaddressedbyTS4.4.4,TendonStressSurveillance.X.X1~X11.X111.X1V.ITS5.7.2.11,InserviceInspectionProgram-requirementsforaninserviceinspectionprogramareaddressedbyTS4.2,InserviceInspection.ITS5.7.2.12,InserviceTestingProgram-requirementsforaninservicetestingprogramareaddressedbyTS4.2.1.6.ITS5.7.2.13,SteamGeneratorTubeSurveillanceProgramandITS5.9.2.e,SpecialReportforSteamGeneratorTubeSurveillanceProgram-requirementsforasteamgeneratortubesurveillanceprogramareaddressedbyTS4.2.1and4.2.1.4.ITS5.7.2.15,VentilationFilterTestingProgram-testingrequirementsforEngineeredSafetyFeaturefilterventilationsystemsisaddressedbyTS4.5.2.3,AirFiltrationSystem.ITS5.7.2.16,ExplosiveGasandStorageTankRadioactivityMonitoringProgram-thecontrolandmonitoringofpotentiallyexplosivegasmixturesinradioactivesystemsisaddressedbyTS3.5.5and3.9.2.5.XV.XV1.ITS5.7.2.17,DieselFuelOilTestingProgram-thecontrol,monitoring,andsamplingrequirementsofdieselfueloilisaddressedbyTS4.6.I.d.ITS5.8.1,SafetyFunctionDeterminationProgram-thisprogramwillbeimplementedfollowingconversionoftheremainingchapters.

ITS5.9.1.6,CoreOperatingLimitsReport-thisreportisonlyrequiredfollowingremovalofexistingtechnicalspecificationcoreoperatinglimitsandwillbeutilizedfollowingconversionoftheremainingsections.xviii.ITS5.9.1.7,ReactorCoolantSystemPressureandTemperatureLimitsReport-thisreportisonlyrequiredfollowingremoval'ofexistingtechnicalspecificationRCSpressureandtemperaturelimitsandwillbeutilizedfollowingconversionoftheremainingsections.ITS5.9.2.b,SpecialReportfollowingfourormorevalidfailuresofanindividualemergencydieselgeneratorsinthelast25demands-ThisrequirementiscurrentlynotspecifiedintheelectricpowersectionsofTechnicalSpecificationsandwillbeaddressedduringtheirconversion.XX.ITS5.9.2.c,SpecialReportrelatedtoPostAccidentMonitoring(PAM)Instrumentation-therequirementforaspecialreportiscurrentlyspecifiedinTSTable3.5-6.ITSAdministrativeControlsNotAddedThefollowingNUREG-1431administrativecontrolrequirementswerenotaddedtothetechnicalspecificationsbasedonITSTravellerBWOG-09orissuesspecifictoGinnaStation:ITS5.1.1(TS6.1.1)-therequirementforPlantManagerapprovalofproposedtests,experimentsormodificationstobecontainedinapprovedadministrativeprocedureswasnotadded.Thiswouldonlyduplicateatechnicalspecificationrequirementwithinproceduresanddoesnotprovideanybenefittosafety.Also,PlantManagerapprovalof"proposedchanges"wasdeletedsincehisapprovalisalreadyrequired"priortoimplementation"whichprovidessufficientcontrolofunitchanges.ITS5.1.2(TS6.1.2)-therequirementforanannualmanagementdirectivetoallstationpersonnelrelatedtotheshiftsupervisorcontrolroomcommandfunctionwasnotadded.AmanagementdirectiveisnotnecessarysincetheauthorityandresponsibilityofeachunitorganizationisspecifiedinthegAProgramandaddressedbyTS6.2.l.a.ITS5.2.2.f-therequirementfortheOperationsManagertoholdanSROlicensewasnotaddedsincethequalificationsofthispositionareaddressedinANSIStandardN18.1-1971(seeTS6.3). v.V1.ITS5.3.1(TS6.3)-arequirementforqualificationsofstaffnotcoveredbyRegulatoryGuide1.8wasnotadded.Thisrequirementwasnotconsiderednecessarysinceallactivitieswhichaffectnuclearsafetyarecontrolledbyothertechnicalspecificationrequirements,existingregulations,andthegAProgram.Also,Revision1ofRegulatoryGuide1.8wasnotrevisedtoRevision2inordertomaintainconsistencywiththecurrentgAProgramandexistingprocedures.ITS5.7.2.9-therequirementforaComponentCyclicorTransientLimitProgramwasnotadded.ThetrackingofcyclicandtransientoccurrenceswithinaspecifiedprogramtoensurethatcomponentsaremaintainedwithinthedesignlimitsisnotconsiderednecessaryduetoexistingprogramssuchassurveillancetestingandtheISIprogram.MaintainingrecordsoftransientandoperationalcyclesiscurrentlyrequiredbyTS6.10.gandthegAProgram.ITS5.7.2.14-therequirementforcontrollingandmonitoringsecondarywaterchemistrywasnotaddedsincethisrequirementisspecifiedasaconditiontotheGinnaStationOperatingLicensedatedDecember10,1984(seeReference12).ITS5.7.2.18-therequirementforaFireProtectionProgramwerenotaddedconsistentwithBWOG-09.Theadministrativecontrolforthisprogramwasoriginallyaddedtoensurethattheunitwascapableofprovidingalternate/dedicatedsafeshutdowninaccordancewith10CFR50,AppendixRfollowingafire.ChangestotheFireProtectionProgrammaybemadewithoutpriorNRCapprovalonlyifthosechangeswouldnotadverselyaffecttheabilitytoachieveandmaintainsafeshutdownintheeventofafire.ThisrequirementisspecifiedasaconditiontotheGinnaStationOperatingLicensedatedDecember10,1984(seeReference13).ChangestoplantproceduresthatimplementtheFireProtectionProgramareaddressedunder10CFR50.59.ITS5.9.2.a-therequirementforaspecialreportfollowingtheactuationandinjectionofanEmergencyCoreCoolingSystem(ECCS)aboveNode4wasnotaddedconsistentwithBWOG-09.ReportingrequirementsrelatedtoECCSactuationsareaddressedby10CFR50.73(a)(2)(iv)whichspecifiesaLicenseeEventReportwithin30days.OtherChangestoTechnicalSpecificationSection6ThefollowingrevisionstotheAdministrativeControlsSection6.0areminorchangesonlyanddonotinvolveanytechnicalissues:ReformatoftheentireSection6.0consistentwiththestructureofNUREG-1431.

r RenumberingofremainingSection6.0requirementsconsistentwiththeformatofNUREG-1431andITSTravellerBWOG-09.1V~v.V1.UpdateofreferencestosectionsoftheCodeofFederalRegulations.StandardizationofreportnameswithinTechnicalSpecifications.RemovalofpreviouslydeletedsectionswithinTechnicalSpecifications.ITS5.l.1(newTS6.1.1)-thewordingwasrevisedtorequirethePlantHanagertoapprovechangesto"structures,systemsorcomponents"thataffectnuclearsafetyconsistentwithGinnaStationterminology.vii.ITS5.1.2(newTS6.1.2)-replaced"valid"licensewith"active"licenseconsistentwithITSTravellerBWOG-09andstandardnomenclatureatGinnaStation.1X.X.ITS5.2.2.e-revisedtheovertimerequirementforunitstaffwhoperformsafetyrelatedfunctionstorequirecontrolinaccordancewithanNRCapprovedprogram.RG&EcurrentlyutilizesastaffworkinghourcontrolprogramwhichslightlydiffersfromtheNRCPolicyStatementonWorkingHours(GenericLetter88-12).ThisprogramwaspreviouslyreviewedandapprovedbytheNRC(Referencell).Theproposedwordingisconsideredmoreappropriateandconsistentwiththecurrenttechnicalspecification.TS6.9.1.1(ITS5.9.1.1)-deletedtherequirementsinceaStartupReportismoreappropriatelyaddressedintheNRCSafetyEvaluationReportauthorizinganOperatingLicense,increasedlicensedpowerlevel,installationofanewnuclearfueldesignormanufacturer,ormodificationswhichsignificantlyalterthenuclear,thermal,orhydraulicperformanceoftheplant.The'StartupReportisrequiredtobesubmittedwithin90daysfollowingcompletionoftheaboveactivitiesanddoesnotrequireNRCapproval.Therefore,inclusionoftherequirementforthisreportinTechnicalSpecificationsisnotnecessarytoassuresafeplantoperation.ITS5.9.1.2.a(newTS6.6.1)-Asubmittaldateof"onorbeforeApril30ofeachyear"wasaddedtotheOccupationalRadiationExposureReportconsistentwith10CFR20.2206(7)(c). xi.ITS5.11(newTS6.7)-replacedreferencesto"healthphysics"with"radiationprotection"throughoutsection.Alsoreplacedthe">1000mrem/hr"with"Z1000mrem/hr"inITS5.11.3tomakeitconsistentwithITS5.11.2.Inaddition,deletedtherequirementfortheRadiationProtectionManagertosignRadiationWorkPermits(RWPs)asspecifiedinITS5.11.I.a.TheissuanceofRWPsisaddressedinproceduresunderthecontrolof10CFR50.59.SpecifyingmanagementpositionsbytitlewithinthetechnicalspecificationscreatesalicenseeandNRCburdenwhentitlesarechangedorresponsibilitiesareshifted.8.RetainedAdministrativeControlRequirementsNotInITSGinnaStationTechnicalSpecification6.7liststherequiredactionsintheeventthataSafetyLimitisviolated.ThisrequirementwillberelocatedtoTechnicalSpecification2.0duringtheconversionoftheremainingsectionstoeliminatetheneedtoreviseadditionaltechnicalspecificationsiftherequirementweretoberelocatednow.SAFETYEVALUATIONThechangesrequestedinthisLARinvolveeither1)therelocationofexistingrequirementswithinthetechnicalspecificationsorotherRGSEcontrolleddocuments,2)eliminationofspecificationsduplicatedbyregulatoryrequirements,3)additionofnewcontrolsinaccordancewithNUREG-1431,or4)administrativechangesonly.ThesechangesareconsistentwiththeFinalPolicyStatementonTechnicalSpecificationsImprovementsforNuclearPowerReactorsandNUREG-1431.Therefore,thesafetyimpactofmakingthesechangeshasbeenpreviouslyconsideredandfoundacceptablebytheNRC.TheAdministrativeControlssectionwasalsoconvertedtotheITSformat;however,notallNUREG-1431requirementswereimplemented.TheseadditionalrequirementswerenotaddedsincetheyarecurrentlyaddressedelsewherewithintheGinnaStationTechnicalSpecifications,aredirectlyrelatedtotheconversionoftheremainingsections,orarenotconsiderednecessarytoprovideacompletespecification.TheimpactofnotimplementingalloftheNUREG-1431requirementswasevaluatedasfollows:ThereisnoincreaseintheprobabilityorconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheUFSARrelatedtonotimplementingalloftheNUREG-1431administrativecontrols.TherequirementswhichwerenotaddedasidentifiedinsectionC.5andC.6abovearecurrentlyaddressedbyexistingtechnicalspecificationsandregulations,theGinnaStationlicense,plantprocedures,orthegAProgram.Therefore,thereisnoincreaseintheprobabilityorconsequencesofanaccidentormalfunctionofequipmentbynotaddingtheserequirementstotheTechnicalSpecifications. ThepossibilityofanewordifferentkindofaccidentoramalfunctionofadifferenttypethanpreviouslyevaluatedintheUFSARisnotcreatedbynotimplementingalloftheNUREG-1431administrativecontrols.TheAdministrativeControlssectioncontainsthoserequirementsthatarenotcoveredbyothertechnicalspecificationswhichareconsiderednecessarytoassuresafeoperationofthefacility.ThesecontrolstypicallysupplementexistingregulationsanddonotaffecttheaccidentanalysescontainedintheUFSAR.SincetheaffectedrequirementsidentifiedinsectionC.5andC.6abovearecurrentlyaddressedbyexistingtechnicalspecificationsandregulations,theGinnaStationlicense,plantprocedures,orthegAProgram,anewordifferentkindofaccidentormalfunctionisnotcreatedbynotaddingthemtotheTechnicalSpecifications.ThereisnoreductioninthemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationrelatedtonotimplementingalloftheNUREG-1431administrativecontrolssincetheserequirementsarecurrentlynotcontainedintheGinnaStationTechnicalSpecifications.Basedontheabove,theproposedamendmentdoesnotinvolveanunreviewedsafetyquestionandwillnotadverselyaffectorendangerthehealthandsafetyofthegeneralpublic.SIGNIFICANTHAZARDSCONSIDERATIONEVALUATIONTheproposedchangestotheGinnaStationTechnicalSpecificationsdonotinvolveasignificanthazardsconsiderationasdiscussedbelow:OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.Thechangesareconsistent,withtheFinalPolicyStatementonTechnicalSpecificationsImprovementsforNuclearPowerReactorsandNUREG-1431andhavetherefore,beenpreviouslyevaluatedbytheNRC.ImplementationofthesechangesisexpectedtoresultinasignificanthumanfactorsimprovementandenableRGEEandtheNRCtofocusonthemostimportantrequirementswithoutanyreductioninsafety.ThechangeswhichdonotduplicateNRCguidanceinNUREG-1431arecurrentlyaddressedbyexistingtechnicalspecificationsandregulations,theGinnaStationlicense,plantprocedures,orthegAProgram.

II,g4Ce044 2.3.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.TheAdministrativeControlssectioncontainsthoserequirementsthatarenotcoveredbyothertechnic'alspecificationswhichareconsiderednecessarytoassuresafeoperationofthefacility.ThemajorityofchangesareconsistentwiththeFinalPolicyStatementonTechnicalSpecificationsImprovementsforNuclearPowerReactorsandNUREG-1431andhavetherefore,beenpreviouslyevaluatedbytheNRC.TherequirementswhichwerenotaddedonlysupplementexistingregulationsanddonotaffecttheaccidentanalysescontainedintheUFSAR.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantreductionin,amarginofsafety.Allrequirementsremovedfromtechnicalspecificationsarerelocatedtootherprogramsanddocuments.Thesealternativeprogramsanddocumentsarecontrolledbyexisting'regulationswhichprovideamoreappropriatevehicleforaddressingchangesandcompliance.Therewerenoadministrativecontrolrequirementswhichwereremovedfromtechnicalspecificationsandnotaddressedbyotherregulations.Therefore,thereisnosignificantreductioninamarginofsafety.Basedupontheaboveinformation,ithasbeendeterminedthattheproposedchangestotheGinnaStationTechnicalSpecificationsdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,doesnotcreatethepossibilityofanewordifferentkindofaccidentpreviouslyevaluated,anddoesnotinvolveasignificantreductioninamarginofsafety.Therefore,itisconcludedthattheproposedchangesmeettherequirementsof10CFR50.92(c)anddonotinvolveasignificanthazardsconsideration.ENVIRONMENTALCONSIDERATIONRG8Ehasevaluatedtheproposedchangesanddeterminedthat:ThechangesdonotinvolveasignificanthazardsconsiderationasdocumentedinSectionEabove;2.Thechangesdonotinvolveasignificantchangeinthetypesorsignificantincreaseintheamountsofanyeffluentsthatmaybereleasedoffsitesincealladministrativecontrolsrelatedtooffsitereleasesareretainedoraddressedbyexistingregulations;and3.Thechangesdonotinvolveasignificantincreaseinindividualorcumulativeoccupationalradiationexposuresincealladministrativecontrolsrelatedtomaintaining'adiationexposureaslowasreasonablyachievableareretainedoraddressedbyexistingregulations.

~4I Accordingly,theproposedchangesmeettheeligibi1itycriteriaforcategoricalexclusionsetforthin10CFR51.22(c)(9).Therefore,pursuantto10CFR51.22(b),anenvironmentalassessmentoftheproposedchangesisnotrequired.REFERENCES2.NUREG-1431,StandardTechnicalSpecifications,kfestinghousePlants,September1993.LetterfromR.C.Hecredy,RG&E,toA.R.Johnson,NRC,

Subject:

ConversiontoImprovedTechnicalSpecifications,datedFebruary28,1994.3.4,5.6.7.8.910.12.13.LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC,

Subject:

ApplicationforAmendmenttoTechnicalSpecification6.5.1,"PlantOperationsReviewCommittee(PORC)Function,"datedMarch23,1993.LetterfromW.T.Russell,NRC,toImprovedTechnicalSpecificationOwnersGroupChairpersons,

Subject:

ContentofStandardTechnicalSpecifications,Section5.0,AdministrativeControls,datedOctober25,1993.ImprovedTechnicalSpecificationTravellerBWOG-09.LetterfromR.W.Kober,RG&E,toH.Fairtile,NRC,

Subject:

PolicyStatementonEngineeringExpertiseonShift(GenericLetter86-04),datedHay14,1986.LetterfromR.CHecredy,RG&E,toA.R.Johnson,NRC,

Subject:

NUREG-0737,Item1.A.1.1,ShiftTechnicalAdvisor,datedOctober12,1989.GenericLetter93-07,

Subject:

HodificationoftheTechnicalSpecificationAdministrativeControlRequirementsforEmergencySecurityPlans.GinnaStat'ionProcedureRD-15.0,OffsiteDoseCalculationHanual.GinnaStationProcedureRD-16.0,ProcessControlProgram.LetterfromW.A.Paulson,NRC,toR.W.Kober,RG&E,

Subject:

PlantStaffirkingHoursandReportingRequirementsforSafetyValveandReliefValveFailuresandChallenges,datedJanuary31,1984.LetterfromD.H.Crutchfield,NRC,toL.D.White,RG&E,

Subject:

IssuanceofAmendmentNo.33toProvisionalOperatingLicenseNo.DPR-18,datedJune13,1980.LetterfromA.R.Johnson,NRC,toR.C.Mecredy,RG&E,

Subject:

IssuanceofAmendmentNo.40toFacilityOperatingLicenseNo.DPR-18,R.E.GinnaNuclearPowerPlant(TACNo.N83568),datedSeptember21,1992.

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