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{{#Wiki_filter:UNITEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSIONIntheMatterof))RochesterGasandElectricCorporation)(R.E.GinnaNuclearPowerPlant)DocketNo.50-244APPLICATIONFORAMENDMENTTOOPERATINGLICENSEANDUALITYASSURANCEPROGRAMPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(NRC),RochesterGasandElectricCorporation(RGEE),holderofFacilityOperatingLicenseNo.DPR-18,herebyrequeststhattheTechnicalSpecificationssetforthinAppendixAtothatlicensebeamended.Thisrequestforchangeistoreplacespecificleakagetestingfrequenciesforcontainmentisolationvalveswithareferenceto10CFR50,AppendixJ,asmodifiedbyapprovedexemptions.Adescriptionoftheamendmentrequest,necessarybackgroundinformation,justificationoftherequestedchange,safetyevaluationandnosignificanthazardsandenvironmentalconsiderationsareprovidedinAttachmentA.Thisevaluationdemonstratesthattheproposedchangedoesnotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeffluentsoranychangeintheauthorizedpowerlevelofthefacility.TheproposedchangealsoTdoesnotinvolveasignificanthazardsconsideration.AmarkedupcopyofthecurrentGinnaStationTechnicalSpecificationswhichshowstherequestedchangeissetforthinAttachmentB.TheproposedrevisedTechnicalSpecificationsareprovidedinAttachmentC.9503ih02089503l3PDRADOCK05000244PPDR WHEREFORE,ApplicantrespectfullyrequeststhatAppendixAtoFacilityOperatingLicenseNo.DPR-18beamendedintheformattachedheretoasAttachmentC.RochesterGasandElectricCorporationByRobertC.HecredyVicePresidentNuclearProductionSubscribedandsworntobeforemeonthis13dayofNarch1995./j~dgNotaryPublic'ikr~.'.~">Lt'Navvy3FATttoa'yt'ublr'c;stateouseCovaotNe>yYo"ionXIExpiresg<t>~+~~
{{#Wiki_filter:UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterof))Rochester GasandElectricCorporation
AttachmentAR.E.GinnaNuclearPowerPlantLicenseAmendmentRequestContainmentIsolationValveTestingFrequencyThisattachmentprovidesadescriptionoftheamendmentrequestandnecessaryjustificationfortheproposedchange.Theattachmentisdividedintosevensectionsasfollows.SectionAidentifiesallchangestothecurrentGinnaStationTechnicalSpecificationswhileSectionBprovidesthebackgroundandhistoryassociatedwiththechangebeingrequested.SectionCprovidesdetailedjustificationfortheproposedchangeincludingacomparisontoImprovedTechnicalSpecificationsasapplicable.Asafetyevaluation,significanthazardsconsiderationevaluation,andenvironmentalconsiderationoftherequestedchangeareprovidedinSectionsD,E,andF,respectively.SectionGlistsallreferencesusedinthisattachment.A.DESCRIPTIONOFAMENDMENTREQUESTThisLicenseAmendmentRequest(LAR)proposestoreviseGinnaStationTechnicalSpecifications(TS)assummarizedbelow.AttachmentBcontainsamarkedupcopyofthecurrentGinnaStationTechnicalSpecificationsshowingtherequestedchange.TheTechnicalSpecificationsfollowingtheproposedchangeisprovidedinAttachmentC.TechnicalSpecification4.4.2.4.ai.Replacespecificleakagetestingfrequenciesforcontainmentisolationvalveswithareferenceto10CFR50,AppendixJ,asmodifiedbyapprovedexemptions.B.BACKGROUND1.HistoryOnFebruary21,1995,theNRCpublishedaproposedrevisionto10CFR50,AppendixJforpubliccomment(Ref.1).Theproposedrevisedrulewouldprovideanoptionforcontainmentleakagetestingwhichispredicatedonusingperformancebasedacceptancecriteria.Assuch,containmentleakagetestingfrequencieswouldbedevelopedbasedontheresultsofprevioustestsinsteadofthecurrentprescriptivefrequencieswhicharenowprovidedin10CFR50,AppendixJ.ThischangeisbeingproposedasaresultofextensiveindustryandNRCevaluationsoftheactualcontainmentleakagetestingresultsinthenuclearpowerindustrywhichdemonstratesthatthecurrentprescriptivetestingfrequenciesaremarginaltosafetyandthataperformancebasedleakagetestprogramisacceptable,andinmanyways,preferable.Thisruleisanticipatedtobeissuedinthefallof1995.  
)(R.E.GinnaNuclearPowerPlant)DocketNo.50-244APPLICATION FORAMENDMENT TOOPERATING LICENSEANDUALITYASSURANCE PROGRAMPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (NRC),Rochester GasandElectricCorporation (RGEE),holderofFacilityOperating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifications setforthinAppendixAtothatlicensebeamended.Thisrequestforchangeistoreplacespecificleakagetestingfrequencies forcontainment isolation valveswithareference to10CFR50,AppendixJ,asmodifiedbyapprovedexemptions.
~~Cp"Ck1gI  Thecurrent(andproposed)10CFR50,AppendixJisorganizedbasedonthreetypesoftests:TypeA,TypeB,andTypeC.TypeAtestsrefertotheoverallcontainmentintegratedleakagerate.TypeBtestsrefertothosecontainmentpenetrationswhichuseisolationbarriersthatincorporateresilientseals,gaskets,sealantcompounds,bellows,orflexiblemetalsealassemblies.TypeCtestsrefertocontainmentisolationvalves.ThisLARproposestorevisethetechnicalspecificationsrelatedtoTypeCpenetrations(i.e.,containmentisolationvalves)toremovetheprescriptivetestingfrequencyinTS4.4.2.4.aof"onceeveryreactorshutdownforrefueling,orotherconvenientintervals,butinnocaseatintervalsgreaterthantwoyears."Thiswillbereplacedwithatestingfrequency"inaccordancewith10CFR50,AppendixJ,asmodifiedbyapprovedexemptions."GinnaStationiscurrentlyon12monthrefuelingcyclessuchthatallcontainmentisolationvalvesaretestedevery12months,whereasplantswithlongeroperatingcycleshavelongertestingintervalsasallowedby10CFR50,AppendixJ.ReplacingthecurrentprescriptivewordingofTS4.4.2.4.aenablesRG&Etorevisethetestingfrequenciesofcontainmentisolationvalvesasallowedby10CFR50.12withoutalsohavingtorequestchangestotechnicalspecifications,since10CFR50,AppendixJmuststillbemet.ThiseliminatesunnecessaryduplicationbetweenthetechnicalspecificationsandtheCodeofFederalRegulationsandprovidesmoreefficientfutureuseofRG&EandNRCresources.RG&Eispursuingtherequestedexemptionsto10CFR50,AppendixJ,SectionIII,D.3concurrentwiththisLARsuchthatcontainmentisolationvalveleakagetestingwouldbeexemptedduringthe1995refuelingoutage.RG&EanticipatesthatGinnaStationwillleaveColdShutdownonApril27,1995atwhichtimecontainmentintegrityisrequiredbyLCO3.6.1.SinceTypeCtestingisrequiredtoensurecontainmentintegrityisavailable,thisLARandthenecessaryexemptionsmustbeapprovedpriortogoingaboveColdShutdownconditions.Assuch,RG&ErequeststhatthisLARbeapprovedpriorto,oron,April27,1995.2.HardwareModificationsTherearenoplantmodificationswhicharerequiredtoimplementthechangesrequestedinthisLAR.This,LARonlyreplacesspecificleakagetestingfrequenciesforcontainmentisolationvalveswithareferenceto10CFR50,AppendixJ,whichprovidesequivalenttestingrequirements.  
Adescription oftheamendment request,necessary background information, justification oftherequested change,safetyevaluation andnosignificant hazardsandenvironmental considerations areprovidedinAttachment A.Thisevaluation demonstrates thattheproposedchangedoesnotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.
~~h'II/  ~C.JUSTIFICATIONThisLARproposestoreplacethecurrentspecifictestingfrequenciesforcontainmentisolationvalvesinTS4.4.2.4.awithareferenceto10CFR50,AppendixJ,asmodifiedbyapprovedexemptions.SectionIII,D.3ofAppendixJprovidesequivalenttestingfrequenciesofcontainmentisolationvalveswiththeexceptionthat"orotherconvenientintervals"isnotspecified.Sincealloperatinglicensesforwater-cooledpowerreactorsarerequiredtomeettherequirementsof10CFR50,AppendixJ,referencingtheactualrequirementinsteadofreiteratingtherequirementswithintechnicalspecificationsprovidesequivalenttestingfrequencies.Inaddition,removingtheactualrequirementsfromtechnicalspecificationspreventstheneedtorevisetechnicalspecificationsastherulechanges,orasexemptionstotherulearegrantedbytheNRC.Removingthereferenceto"orotherconvenientintervals"alsoeliminatespotentialconflictwith10CFR50,AppendixJsincethisisnotanallowedoptionforTypeCtests.TheproposedchangeisalsoconsistentwithLCO3.6.1,"Containment,"ofNUREG-1431(Ref.2)inthatSurveillanceSR3.6.l.1requirestestingofcontainmentisolationvalves"inaccordancewith10CFR50,AppendixJ,asmodifiedbyapprovedexemptions."D.SAFETYEVALUATIONThechangerequestedinthisLARinvolvesreplacingspecificleakagetestingfrequenciesforcontainmentisolationvalveswithareferenceto10CFR50,AppendixJ,asmodifiedbyapprovedexemptions.ThischangeisconsistentwiththeNRCapprovedImprovedStandardTechnicalSpecificationsforWestinghouseplants(Ref.2).Therefore,thesafetyimpactofmakingthischangehasbeenpreviouslyconsideredandfoundgenericallyacceptablebytheNRC.Theplantspecificevaluationofthischangeisprovidedbelow.ThereisnoincreaseintheprobabilityorconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheUFSARrelatedtothischange.10CFR50,AppendixJprovidesequivalenttestingfrequenciesasthecurrentGinnaStationtechnicalspecificationssuchthatcontainmentintegrityrequirementswillstillbemaintained.AnychangetothesetestingfrequenciesstillrequirespriorNRCapprovalsuchthatthereisnoincreaseintheprobabilityorconsequencesofanaccidentormalfunctionofequipment.ThepossibilityofanewordifferentkindofaccidentoramalfunctionofadifferenttypethanpreviouslyevaluatedintheUFSARisnotcreatedbytheproposedchange.ThecontainmentisolationvalvesarestillrequiredtobetestedtoensurecontainmentintegritycanbemetaboveColdShutdown;onlythetestingfrequencyisbeingreplacedwithareferencetotheCodeofFederalRegulations.Assuch,anewordifferentkindofaccidentormalfunctionisnotcreatedbyreferencinginsteadofreiteratingthetestingfrequencywithintechnicalspecifications.
TheproposedchangealsoTdoesnotinvolveasignificant hazardsconsideration.
ThereisnoreductioninthemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationsincethecontainmentisolationvalveleakagetestingrequirementsareonlybeingreplacedwithareferenceto10CFR50,AppendixJwhichprovidesequivalentcontrols.Basedontheabove,theproposedamendmentdoesnotinvolveanunreviewedsafetyquestionandwillnotadverselyaffectorendangerthehealthandsafetyofthegeneralpublic.SIGNIFICANTHAZARDSCONSIDERATIONEVALUATIONTheproposedchangestotheGinnaStationTechnicalSpecificationsdonotinvolveasignificanthazardsconsiderationasdiscussedbelow:OperationofGinnaStationinaccordancewiththeproposedchangedoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.ThechangeisconsistentwithNUREG-1431andhastherefore,beenpreviouslyevaluatedandacceptedbytheNRC.ThechangeinvolvesnotechnicalchangetotheexistingTechnicalSpecificationsince10CFRAppendixJprovidesequivalenttestingfrequenciesasthosecurrentlyspecifiedinTS4.4.2.4.a.Thereisnoimpacttoinitiatorsofanalyzedeventsorassumedmitigationofaccidentontransientevents.ImplementationofthischangeisexpectedtoresultinmoreefficientuseofRG&EandtheNRCresourceswithoutanyreductioninsafety.2.OperationofGinnaStationinaccordancewiththeproposedchangedoesnotcreatethe.possibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.ThechangeisconsistentwithNUREG-1431andhastherefore,beenpreviouslyevaluatedandacceptedbytheNRC.Thechangedoesnotinvolvephysicalalterationsoftheplant(nonewordifferenttypeofequipmentwillbeinstalled)orchangesinmethodsgoverningnormalplantoperation.Thechangedoesnotimposeoreliminateanynewordifferentrequirementssince10CFR50,AppendixJprovidesequivalenttestingfrequenciesasthosecurrentlyspecifiedinTS4.4.2.4.a.3.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantreductioninamarginofsafety.Allrequirementsinthetechnicalspecificationsrelatedtocontainmentisolationvalvesremainthesamewiththeexceptionthatareferenceto10CFR50,AppendixJisbeingprovidedinplaceofspecificleakagetesting'equirements.Thechangehasnoimpactonanysafetyanalysisassumptions.
AmarkedupcopyofthecurrentGinnaStationTechnical Specifications whichshowstherequested changeissetforthinAttachment B.TheproposedrevisedTechnical Specifications areprovidedinAttachment C.9503ih0208 9503l3PDRADOCK05000244PPDR WHEREFORE, Applicant respectfully requeststhatAppendixAtoFacilityOperating LicenseNo.DPR-18beamendedintheformattachedheretoasAttachment C.Rochester GasandElectricCorporation ByRobertC.HecredyVicePresident NuclearProduction Subscribed andsworntobeforemeonthis13dayofNarch1995./j~dgNotaryPublic'ikr~.'.~">Lt'Navvy 3FATttoa'yt'ublr'c; stateouseCovaotNe>yYo"ionXIExpiresg<t>~+~~
P  Basedupontheaboveinformation,ithasbeendeterminedthattheproposedchangetotheGinnaStationTechnicalSpecificationsdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,doesnotcreatethepossibilityofanewordifferentkindofaccidentpreviouslyevaluated,anddoesnotinvolveasignificantreductioninamarginofsafety.Therefore,itisconcludedthattheproposedchangesmeettherequirementsof10CFR50.92(c)anddonotinvolveasignificanthazardsconsideration.ENVIRONMENTALCONSIDERATIONRGLEhasevaluatedtheproposedchangesanddeterminedthat:1.ThechangedoesnotinvolveasignificanthazardsconsiderationasdocumentedinSectionEabove;2.3.Thechangedoesnotinvolveasignificantchangeinthetypesorsignificantincreaseintheamountsofanyeffluentsthatmaybereleasedoffsitesincetheproposedchangedoesnotmodifyanycontainmentintegrityrequirements;andThechangedoesnotinvolveasignificantincreaseinindividualorcumulativeoccupationalradiationexposuresincecontainmentisolationvalvetestingfrequenciesascontainedin10CFR50,Appendix0areequivalenttothoseinthecurrenttechnicalspecifications.Accordingly,theproposedchangesmeettheeligibilitycriteriaforcategoricalexclusionsetforthin10CFR51.22(c)(9).Therefore,pursuantto10CFR51.22(b),anenvironmentalassessmentoftheproposedchangesisnotrequired.REFERENCES1.FederalRegister,Volume60,page9634,February21,1995.2.NUREG-1431,StandardTechnicalSpecifications,westinghousePlants,September1992.}}
Attachment AR.E.GinnaNuclearPowerPlantLicenseAmendment RequestContainment Isolation ValveTestingFrequency Thisattachment providesadescription oftheamendment requestandnecessary justification fortheproposedchange.Theattachment isdividedintosevensectionsasfollows.SectionAidentifies allchangestothecurrentGinnaStationTechnical Specifications whileSectionBprovidesthebackground andhistoryassociated withthechangebeingrequested.
SectionCprovidesdetailedjustification fortheproposedchangeincluding acomparison toImprovedTechnical Specifications asapplicable.
Asafetyevaluation, significant hazardsconsideration evaluation, andenvironmental consideration oftherequested changeareprovidedinSectionsD,E,andF,respectively.
SectionGlistsallreferences usedinthisattachment.
A.DESCRIPTION OFAMENDMENT REQUESTThisLicenseAmendment Request(LAR)proposestoreviseGinnaStationTechnical Specifications (TS)assummarized below.Attachment BcontainsamarkedupcopyofthecurrentGinnaStationTechnical Specifications showingtherequested change.TheTechnical Specifications following theproposedchangeisprovidedinAttachment C.Technical Specification 4.4.2.4.a i.Replacespecificleakagetestingfrequencies forcontainment isolation valveswithareference to10CFR50,AppendixJ,asmodifiedbyapprovedexemptions.
B.BACKGROUND 1.HistoryOnFebruary21,1995,theNRCpublished aproposedrevisionto10CFR50,AppendixJforpubliccomment(Ref.1).Theproposedrevisedrulewouldprovideanoptionforcontainment leakagetestingwhichispredicated onusingperformance basedacceptance criteria.
Assuch,containment leakagetestingfrequencies wouldbedeveloped basedontheresultsofprevioustestsinsteadofthecurrentprescriptive frequencies whicharenowprovidedin10CFR50,AppendixJ.Thischangeisbeingproposedasaresultofextensive industryandNRCevaluations oftheactualcontainment leakagetestingresultsinthenuclearpowerindustrywhichdemonstrates thatthecurrentprescriptive testingfrequencies aremarginaltosafetyandthataperformance basedleakagetestprogramisacceptable, andinmanyways,preferable.
Thisruleisanticipated tobeissuedinthefallof1995.  
~~Cp"Ck1gI  Thecurrent(andproposed) 10CFR50,AppendixJisorganized basedonthreetypesoftests:TypeA,TypeB,andTypeC.TypeAtestsrefertotheoverallcontainment integrated leakagerate.TypeBtestsrefertothosecontainment penetrations whichuseisolation barriersthatincorporate resilient seals,gaskets,sealantcompounds, bellows,orflexiblemetalsealassemblies.
TypeCtestsrefertocontainment isolation valves.ThisLARproposestorevisethetechnical specifications relatedtoTypeCpenetrations (i.e.,containment isolation valves)toremovetheprescriptive testingfrequency inTS4.4.2.4.a of"onceeveryreactorshutdownforrefueling, orotherconvenient intervals, butinnocaseatintervals greaterthantwoyears."Thiswillbereplacedwithatestingfrequency "inaccordance with10CFR50,AppendixJ,asmodifiedbyapprovedexemptions."
GinnaStationiscurrently on12monthrefueling cyclessuchthatallcontainment isolation valvesaretestedevery12months,whereasplantswithlongeroperating cycleshavelongertestingintervals asallowedby10CFR50,AppendixJ.Replacing thecurrentprescriptive wordingofTS4.4.2.4.a enablesRG&Etorevisethetestingfrequencies ofcontainment isolation valvesasallowedby10CFR50.12withoutalsohavingtorequestchangestotechnical specifications, since10CFR50,AppendixJmuststillbemet.Thiseliminates unnecessary duplication betweenthetechnical specifications andtheCodeofFederalRegulations andprovidesmoreefficient futureuseofRG&EandNRCresources.
RG&Eispursuingtherequested exemptions to10CFR50,AppendixJ,SectionIII,D.3concurrent withthisLARsuchthatcontainment isolation valveleakagetestingwouldbeexemptedduringthe1995refueling outage.RG&Eanticipates thatGinnaStationwillleaveColdShutdownonApril27,1995atwhichtimecontainment integrity isrequiredbyLCO3.6.1.SinceTypeCtestingisrequiredtoensurecontainment integrity isavailable, thisLARandthenecessary exemptions mustbeapprovedpriortogoingaboveColdShutdownconditions.
Assuch,RG&ErequeststhatthisLARbeapprovedpriorto,oron,April27,1995.2.HardwareModifications Therearenoplantmodifications whicharerequiredtoimplement thechangesrequested inthisLAR.This,LARonlyreplacesspecificleakagetestingfrequencies forcontainment isolation valveswithareference to10CFR50,AppendixJ,whichprovidesequivalent testingrequirements.  
~~h'II/  ~C.JUSTIFICATION ThisLARproposestoreplacethecurrentspecifictestingfrequencies forcontainment isolation valvesinTS4.4.2.4.a withareference to10CFR50,AppendixJ,asmodifiedbyapprovedexemptions.
SectionIII,D.3ofAppendixJprovidesequivalent testingfrequencies ofcontainment isolation valveswiththeexception that"orotherconvenient intervals" isnotspecified.
Sincealloperating licensesforwater-cooled powerreactorsarerequiredtomeettherequirements of10CFR50,AppendixJ,referencing theactualrequirement insteadofreiterating therequirements withintechnical specifications providesequivalent testingfrequencies.
Inaddition, removingtheactualrequirements fromtechnical specifications preventstheneedtorevisetechnical specifications astherulechanges,orasexemptions totherulearegrantedbytheNRC.Removingthereference to"orotherconvenient intervals" alsoeliminates potential conflictwith10CFR50,AppendixJsincethisisnotanallowedoptionforTypeCtests.Theproposedchangeisalsoconsistent withLCO3.6.1,"Containment,"
ofNUREG-1431 (Ref.2)inthatSurveillance SR3.6.l.1requirestestingofcontainment isolation valves"inaccordance with10CFR50,AppendixJ,asmodifiedbyapprovedexemptions."
D.SAFETYEVALUATION Thechangerequested inthisLARinvolvesreplacing specificleakagetestingfrequencies forcontainment isolation valveswithareference to10CFR50,AppendixJ,asmodifiedbyapprovedexemptions.
Thischangeisconsistent withtheNRCapprovedImprovedStandardTechnical Specifications forWestinghouse plants(Ref.2).Therefore, thesafetyimpactofmakingthischangehasbeenpreviously considered andfoundgenerically acceptable bytheNRC.Theplantspecificevaluation ofthischangeisprovidedbelow.Thereisnoincreaseintheprobability orconsequences ofanaccidentormalfunction ofequipment important tosafetypreviously evaluated intheUFSARrelatedtothischange.10CFR50,AppendixJprovidesequivalent testingfrequencies asthecurrentGinnaStationtechnical specifications suchthatcontainment integrity requirements willstillbemaintained.
Anychangetothesetestingfrequencies stillrequirespriorNRCapprovalsuchthatthereisnoincreaseintheprobability orconsequences ofanaccidentormalfunction ofequipment.
Thepossibility ofanewordifferent kindofaccidentoramalfunction ofadifferent typethanpreviously evaluated intheUFSARisnotcreatedbytheproposedchange.Thecontainment isolation valvesarestillrequiredtobetestedtoensurecontainment integrity canbemetaboveColdShutdown; onlythetestingfrequency isbeingreplacedwithareference totheCodeofFederalRegulations.
Assuch,anewordifferent kindofaccidentormalfunction isnotcreatedbyreferencing insteadofreiterating thetestingfrequency withintechnical specifications.
Thereisnoreduction inthemarginofsafetyasdefinedinthebasisforanyTechnical Specification sincethecontainment isolation valveleakagetestingrequirements areonlybeingreplacedwithareference to10CFR50,AppendixJwhichprovidesequivalent controls.
Basedontheabove,theproposedamendment doesnotinvolveanunreviewed safetyquestionandwillnotadversely affectorendangerthehealthandsafetyofthegeneralpublic.SIGNIFICANT HAZARDSCONSIDERATION EVALUATION TheproposedchangestotheGinnaStationTechnical Specifications donotinvolveasignificant hazardsconsideration asdiscussed below:Operation ofGinnaStationinaccordance withtheproposedchangedoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
Thechangeisconsistent withNUREG-1431 andhastherefore, beenpreviously evaluated andacceptedbytheNRC.Thechangeinvolvesnotechnical changetotheexistingTechnical Specification since10CFRAppendixJprovidesequivalent testingfrequencies asthosecurrently specified inTS4.4.2.4.a.
Thereisnoimpacttoinitiators ofanalyzedeventsorassumedmitigation ofaccidentontransient events.Implementation ofthischangeisexpectedtoresultinmoreefficient useofRG&EandtheNRCresources withoutanyreduction insafety.2.Operation ofGinnaStationinaccordance withtheproposedchangedoesnotcreatethe.possibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Thechangeisconsistent withNUREG-1431 andhastherefore, beenpreviously evaluated andacceptedbytheNRC.Thechangedoesnotinvolvephysicalalterations oftheplant(nonewordifferent typeofequipment willbeinstalled) orchangesinmethodsgoverning normalplantoperation.
Thechangedoesnotimposeoreliminate anynewordifferent requirements since10CFR50,AppendixJprovidesequivalent testingfrequencies asthosecurrently specified inTS4.4.2.4.a.
3.Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant reduction inamarginofsafety.Allrequirements inthetechnical specifications relatedtocontainment isolation valvesremainthesamewiththeexception thatareference to10CFR50,AppendixJisbeingprovidedinplaceofspecificleakagetesting'equirements.
Thechangehasnoimpactonanysafetyanalysisassumptions.
P  Basedupontheaboveinformation, ithasbeendetermined thattheproposedchangetotheGinnaStationTechnical Specifications doesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, doesnotcreatethepossibility ofanewordifferent kindofaccidentpreviously evaluated, anddoesnotinvolveasignificant reduction inamarginofsafety.Therefore, itisconcluded thattheproposedchangesmeettherequirements of10CFR50.92(c)anddonotinvolveasignificant hazardsconsideration.
ENVIRONMENTAL CONSIDERATION RGLEhasevaluated theproposedchangesanddetermined that:1.Thechangedoesnotinvolveasignificant hazardsconsideration asdocumented inSectionEabove;2.3.Thechangedoesnotinvolveasignificant changeinthetypesorsignificant increaseintheamountsofanyeffluents thatmaybereleasedoffsitesincetheproposedchangedoesnotmodifyanycontainment integrity requirements; andThechangedoesnotinvolveasignificant increaseinindividual orcumulative occupational radiation exposuresincecontainment isolation valvetestingfrequencies ascontained in10CFR50,Appendix0areequivalent tothoseinthecurrenttechnical specifications.
Accordingly, theproposedchangesmeettheeligibility criteriaforcategorical exclusion setforthin10CFR51.22(c)(9).
Therefore, pursuantto10CFR51.22(b),
anenvironmental assessment oftheproposedchangesisnotrequired.
REFERENCES 1.FederalRegister, Volume60,page9634,February21,1995.2.NUREG-1431, StandardTechnical Specifications, westinghouse Plants,September 1992.}}

Revision as of 11:54, 29 June 2018

Application for Amend to License DPR-18,to Revise TS 4.4.2.4.a to Replace Specific Leakage Testing Frequencies for Containment Isolation Valves
ML17263A977
Person / Time
Site: Ginna 
Issue date: 03/13/1995
From: MECREDY R C
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A976 List:
References
NUDOCS 9503160208
Download: ML17263A977 (10)
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Text

UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterof))Rochester GasandElectricCorporation

)(R.E.GinnaNuclearPowerPlant)DocketNo.50-244APPLICATION FORAMENDMENT TOOPERATING LICENSEANDUALITYASSURANCE PROGRAMPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (NRC),Rochester GasandElectricCorporation (RGEE),holderofFacilityOperating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifications setforthinAppendixAtothatlicensebeamended.Thisrequestforchangeistoreplacespecificleakagetestingfrequencies forcontainment isolation valveswithareference to10CFR50,AppendixJ,asmodifiedbyapprovedexemptions.

Adescription oftheamendment request,necessary background information, justification oftherequested change,safetyevaluation andnosignificant hazardsandenvironmental considerations areprovidedinAttachment A.Thisevaluation demonstrates thattheproposedchangedoesnotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.

TheproposedchangealsoTdoesnotinvolveasignificant hazardsconsideration.

AmarkedupcopyofthecurrentGinnaStationTechnical Specifications whichshowstherequested changeissetforthinAttachment B.TheproposedrevisedTechnical Specifications areprovidedinAttachment C.9503ih0208 9503l3PDRADOCK05000244PPDR WHEREFORE, Applicant respectfully requeststhatAppendixAtoFacilityOperating LicenseNo.DPR-18beamendedintheformattachedheretoasAttachment C.Rochester GasandElectricCorporation ByRobertC.HecredyVicePresident NuclearProduction Subscribed andsworntobeforemeonthis13dayofNarch1995./j~dgNotaryPublic'ikr~.'.~">Lt'Navvy 3FATttoa'yt'ublr'c; stateouseCovaotNe>yYo"ionXIExpiresg<t>~+~~

Attachment AR.E.GinnaNuclearPowerPlantLicenseAmendment RequestContainment Isolation ValveTestingFrequency Thisattachment providesadescription oftheamendment requestandnecessary justification fortheproposedchange.Theattachment isdividedintosevensectionsasfollows.SectionAidentifies allchangestothecurrentGinnaStationTechnical Specifications whileSectionBprovidesthebackground andhistoryassociated withthechangebeingrequested.

SectionCprovidesdetailedjustification fortheproposedchangeincluding acomparison toImprovedTechnical Specifications asapplicable.

Asafetyevaluation, significant hazardsconsideration evaluation, andenvironmental consideration oftherequested changeareprovidedinSectionsD,E,andF,respectively.

SectionGlistsallreferences usedinthisattachment.

A.DESCRIPTION OFAMENDMENT REQUESTThisLicenseAmendment Request(LAR)proposestoreviseGinnaStationTechnical Specifications (TS)assummarized below.Attachment BcontainsamarkedupcopyofthecurrentGinnaStationTechnical Specifications showingtherequested change.TheTechnical Specifications following theproposedchangeisprovidedinAttachment C.Technical Specification 4.4.2.4.a i.Replacespecificleakagetestingfrequencies forcontainment isolation valveswithareference to10CFR50,AppendixJ,asmodifiedbyapprovedexemptions.

B.BACKGROUND 1.HistoryOnFebruary21,1995,theNRCpublished aproposedrevisionto10CFR50,AppendixJforpubliccomment(Ref.1).Theproposedrevisedrulewouldprovideanoptionforcontainment leakagetestingwhichispredicated onusingperformance basedacceptance criteria.

Assuch,containment leakagetestingfrequencies wouldbedeveloped basedontheresultsofprevioustestsinsteadofthecurrentprescriptive frequencies whicharenowprovidedin10CFR50,AppendixJ.Thischangeisbeingproposedasaresultofextensive industryandNRCevaluations oftheactualcontainment leakagetestingresultsinthenuclearpowerindustrywhichdemonstrates thatthecurrentprescriptive testingfrequencies aremarginaltosafetyandthataperformance basedleakagetestprogramisacceptable, andinmanyways,preferable.

Thisruleisanticipated tobeissuedinthefallof1995.

~~Cp"Ck1gI Thecurrent(andproposed) 10CFR50,AppendixJisorganized basedonthreetypesoftests:TypeA,TypeB,andTypeC.TypeAtestsrefertotheoverallcontainment integrated leakagerate.TypeBtestsrefertothosecontainment penetrations whichuseisolation barriersthatincorporate resilient seals,gaskets,sealantcompounds, bellows,orflexiblemetalsealassemblies.

TypeCtestsrefertocontainment isolation valves.ThisLARproposestorevisethetechnical specifications relatedtoTypeCpenetrations (i.e.,containment isolation valves)toremovetheprescriptive testingfrequency inTS4.4.2.4.a of"onceeveryreactorshutdownforrefueling, orotherconvenient intervals, butinnocaseatintervals greaterthantwoyears."Thiswillbereplacedwithatestingfrequency "inaccordance with10CFR50,AppendixJ,asmodifiedbyapprovedexemptions."

GinnaStationiscurrently on12monthrefueling cyclessuchthatallcontainment isolation valvesaretestedevery12months,whereasplantswithlongeroperating cycleshavelongertestingintervals asallowedby10CFR50,AppendixJ.Replacing thecurrentprescriptive wordingofTS4.4.2.4.a enablesRG&Etorevisethetestingfrequencies ofcontainment isolation valvesasallowedby10CFR50.12withoutalsohavingtorequestchangestotechnical specifications, since10CFR50,AppendixJmuststillbemet.Thiseliminates unnecessary duplication betweenthetechnical specifications andtheCodeofFederalRegulations andprovidesmoreefficient futureuseofRG&EandNRCresources.

RG&Eispursuingtherequested exemptions to10CFR50,AppendixJ,SectionIII,D.3concurrent withthisLARsuchthatcontainment isolation valveleakagetestingwouldbeexemptedduringthe1995refueling outage.RG&Eanticipates thatGinnaStationwillleaveColdShutdownonApril27,1995atwhichtimecontainment integrity isrequiredbyLCO3.6.1.SinceTypeCtestingisrequiredtoensurecontainment integrity isavailable, thisLARandthenecessary exemptions mustbeapprovedpriortogoingaboveColdShutdownconditions.

Assuch,RG&ErequeststhatthisLARbeapprovedpriorto,oron,April27,1995.2.HardwareModifications Therearenoplantmodifications whicharerequiredtoimplement thechangesrequested inthisLAR.This,LARonlyreplacesspecificleakagetestingfrequencies forcontainment isolation valveswithareference to10CFR50,AppendixJ,whichprovidesequivalent testingrequirements.

~~h'II/ ~C.JUSTIFICATION ThisLARproposestoreplacethecurrentspecifictestingfrequencies forcontainment isolation valvesinTS4.4.2.4.a withareference to10CFR50,AppendixJ,asmodifiedbyapprovedexemptions.

SectionIII,D.3ofAppendixJprovidesequivalent testingfrequencies ofcontainment isolation valveswiththeexception that"orotherconvenient intervals" isnotspecified.

Sincealloperating licensesforwater-cooled powerreactorsarerequiredtomeettherequirements of10CFR50,AppendixJ,referencing theactualrequirement insteadofreiterating therequirements withintechnical specifications providesequivalent testingfrequencies.

Inaddition, removingtheactualrequirements fromtechnical specifications preventstheneedtorevisetechnical specifications astherulechanges,orasexemptions totherulearegrantedbytheNRC.Removingthereference to"orotherconvenient intervals" alsoeliminates potential conflictwith10CFR50,AppendixJsincethisisnotanallowedoptionforTypeCtests.Theproposedchangeisalsoconsistent withLCO3.6.1,"Containment,"

ofNUREG-1431 (Ref.2)inthatSurveillance SR3.6.l.1requirestestingofcontainment isolation valves"inaccordance with10CFR50,AppendixJ,asmodifiedbyapprovedexemptions."

D.SAFETYEVALUATION Thechangerequested inthisLARinvolvesreplacing specificleakagetestingfrequencies forcontainment isolation valveswithareference to10CFR50,AppendixJ,asmodifiedbyapprovedexemptions.

Thischangeisconsistent withtheNRCapprovedImprovedStandardTechnical Specifications forWestinghouse plants(Ref.2).Therefore, thesafetyimpactofmakingthischangehasbeenpreviously considered andfoundgenerically acceptable bytheNRC.Theplantspecificevaluation ofthischangeisprovidedbelow.Thereisnoincreaseintheprobability orconsequences ofanaccidentormalfunction ofequipment important tosafetypreviously evaluated intheUFSARrelatedtothischange.10CFR50,AppendixJprovidesequivalent testingfrequencies asthecurrentGinnaStationtechnical specifications suchthatcontainment integrity requirements willstillbemaintained.

Anychangetothesetestingfrequencies stillrequirespriorNRCapprovalsuchthatthereisnoincreaseintheprobability orconsequences ofanaccidentormalfunction ofequipment.

Thepossibility ofanewordifferent kindofaccidentoramalfunction ofadifferent typethanpreviously evaluated intheUFSARisnotcreatedbytheproposedchange.Thecontainment isolation valvesarestillrequiredtobetestedtoensurecontainment integrity canbemetaboveColdShutdown; onlythetestingfrequency isbeingreplacedwithareference totheCodeofFederalRegulations.

Assuch,anewordifferent kindofaccidentormalfunction isnotcreatedbyreferencing insteadofreiterating thetestingfrequency withintechnical specifications.

Thereisnoreduction inthemarginofsafetyasdefinedinthebasisforanyTechnical Specification sincethecontainment isolation valveleakagetestingrequirements areonlybeingreplacedwithareference to10CFR50,AppendixJwhichprovidesequivalent controls.

Basedontheabove,theproposedamendment doesnotinvolveanunreviewed safetyquestionandwillnotadversely affectorendangerthehealthandsafetyofthegeneralpublic.SIGNIFICANT HAZARDSCONSIDERATION EVALUATION TheproposedchangestotheGinnaStationTechnical Specifications donotinvolveasignificant hazardsconsideration asdiscussed below:Operation ofGinnaStationinaccordance withtheproposedchangedoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

Thechangeisconsistent withNUREG-1431 andhastherefore, beenpreviously evaluated andacceptedbytheNRC.Thechangeinvolvesnotechnical changetotheexistingTechnical Specification since10CFRAppendixJprovidesequivalent testingfrequencies asthosecurrently specified inTS4.4.2.4.a.

Thereisnoimpacttoinitiators ofanalyzedeventsorassumedmitigation ofaccidentontransient events.Implementation ofthischangeisexpectedtoresultinmoreefficient useofRG&EandtheNRCresources withoutanyreduction insafety.2.Operation ofGinnaStationinaccordance withtheproposedchangedoesnotcreatethe.possibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Thechangeisconsistent withNUREG-1431 andhastherefore, beenpreviously evaluated andacceptedbytheNRC.Thechangedoesnotinvolvephysicalalterations oftheplant(nonewordifferent typeofequipment willbeinstalled) orchangesinmethodsgoverning normalplantoperation.

Thechangedoesnotimposeoreliminate anynewordifferent requirements since10CFR50,AppendixJprovidesequivalent testingfrequencies asthosecurrently specified inTS4.4.2.4.a.

3.Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant reduction inamarginofsafety.Allrequirements inthetechnical specifications relatedtocontainment isolation valvesremainthesamewiththeexception thatareference to10CFR50,AppendixJisbeingprovidedinplaceofspecificleakagetesting'equirements.

Thechangehasnoimpactonanysafetyanalysisassumptions.

P Basedupontheaboveinformation, ithasbeendetermined thattheproposedchangetotheGinnaStationTechnical Specifications doesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, doesnotcreatethepossibility ofanewordifferent kindofaccidentpreviously evaluated, anddoesnotinvolveasignificant reduction inamarginofsafety.Therefore, itisconcluded thattheproposedchangesmeettherequirements of10CFR50.92(c)anddonotinvolveasignificant hazardsconsideration.

ENVIRONMENTAL CONSIDERATION RGLEhasevaluated theproposedchangesanddetermined that:1.Thechangedoesnotinvolveasignificant hazardsconsideration asdocumented inSectionEabove;2.3.Thechangedoesnotinvolveasignificant changeinthetypesorsignificant increaseintheamountsofanyeffluents thatmaybereleasedoffsitesincetheproposedchangedoesnotmodifyanycontainment integrity requirements; andThechangedoesnotinvolveasignificant increaseinindividual orcumulative occupational radiation exposuresincecontainment isolation valvetestingfrequencies ascontained in10CFR50,Appendix0areequivalent tothoseinthecurrenttechnical specifications.

Accordingly, theproposedchangesmeettheeligibility criteriaforcategorical exclusion setforthin10CFR51.22(c)(9).

Therefore, pursuantto10CFR51.22(b),

anenvironmental assessment oftheproposedchangesisnotrequired.

REFERENCES 1.FederalRegister, Volume60,page9634,February21,1995.2.NUREG-1431, StandardTechnical Specifications, westinghouse Plants,September 1992.

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