ML17262A413
| ML17262A413 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/08/1991 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17262A411 | List: |
| References | |
| NUDOCS 9103140015 | |
| Download: ML17262A413 (16) | |
Text
ATTACHMENTARevisetheTechnicalSpecificationpagesasfollows:Remove3.6-23.6-33.6-43.6-53.6-63.6-73.6-7A3.6-83.6-93.6-103.6-114~444.4-74.4-84.4-11Insert3.6-23.6-34~444.4-74.4-84.4-11gOP0244'DPQQOGK@DE 3.6.33.6.3.1ContainmentIsolationValvesWithoneormorecontainmentisolationvalvesinoperable,maintainatleastoneisolationboundaryOPERABLEineachaffectedpenetrationthatisopenandeither:a.Restoretheinoperablevalve(s)tooperablestatuswithin4hours,orb.Isolateeachaffectedpenetrationwithin4hoursbyuseofatleastonedeactivatedautomaticvalvesecuredintheisolationposition,or3.6.43.6.4.13.6.4.2c.Isolateeachaffectedpenetrationwithin4hoursbyuseofat,leastoneclosedmanualvalveorblindflange,ord.Beinatleasthotshutdownwithinthenext6hoursandincoldshutdownwithinthefollowing30hours.Containmentisolationvalvesareinoperablefromaleakagestandpointwhenthedemonstratedleakageofasinglecontainmentisolationvalveorcumulativetotalleakageofallcontainmentisolationvalvesisgreaterthanthatallowedby10CPR50AppendixJ.CombustibleGasControlWhenthereactoriscritical,atleasttwoindependentcontainmenthydrogenmonitorsshallbeoperable.OneofthemonitorsmaybethePostAccidentSamplingSystem.Withonlyonehydrogenmonitoroperable,restoreasecondmonitortooperablestatuswithin30daysorbeinatleasthotshutdownwithinthenext.6hours.3.6.4.3Withnohydrogenmonitorsoperable,restoreatleastonemonitortooperablestatuswithin72hoursorbeinatleasthotshutdownwithinthenext,6hours.3.6.5ContainmentMini-PureWheneverthecontainmentintegrityisrequired,emphasiswillbeplacedonlimitingallpurgingandventingtimestoaslowasachievable.Themini-purgeisolationvalveswillremainclosedtothemaximumextentpracticablebutmaybeopenforpressurecontrol,forALARA,forrespirableairqualityconsiderationsforpersonnelentry,forsurveillanceteststhatmayrequirethevalvetobeopenorothersafetyrelatedreasons.AmendmentNo.X83.6-2Proposed Basis:Thereactorcoolantsystemconditionsofcoldshutdownassurethatnosteamwillbeformedandhencetherewouldbenopressurebuildupinthecontainmentifthereactorcoolantsystemruptures.Theshutdownmarginsareselectedbasedonthetypeofactivitiesthatarebeingcarriedout.The(2000ppm)boronconcentrationprovidesshutdownmarginwhichprecludescriticalityunderanycircumstances.Whenthereactorheadisnottoberemoved,acoldshutdownmarginof14k/kprecludescriticalityinanyoccurrence.Regardinginternalpressurelimitations,thecontainment,designpressureof60psigwouldnotbeexceedediftheinternalpressurebeforeamajorsteambreakaccidentwereasmuchas1psig.'"Thecontainmentisdesignedtowithstandaninternalvacuumof2.5psig.<'>The2.0psigvacuumisspecifiedasanoperatinglimittoavoidanydifficulties.withmotorcooling.ContainmentisolationvalvesandboundariesarelistedinUFSARTable6.2-13.Isolationboundariescanincludeisolationvalves,closedsystems,andflangesasshownonUFSARTable6.2-13.
References:
(1)WestinghouseAnalysis,"ReportfortheBASTConcentrationReduction",.August1985(2)UFSAR-Section3.8.1.2.2(3)UFSARTable6.2-133.6-3Proposed AccetanceCriteriaa~b.TheleakagerateLtmshallbe<0.75LtatPt.Ptisdefinedasthecontainmentvesselreducedtestpressurewhichisgreaterthanorequalto35psig.LtmisdefinedasthetotalmeasuredcontainmentleakagerateatpressurePt.LtisdefinedasthemaximumallowableleakagerateatpressurePt.Lt'shallbedeterminedasLe=La-whichequalsSC~/2Za1528percentweightperdayat35psig.Paisdefinedasthecalculatedpeakcontainmentinternalpressurerelatedtodesignbasisaccidentswhichisgreaterthanorequalto60psig.LaisdefinedasthemaximumallowableleakagerateatPawhichequals.2percentweightperday.C~TheleakagerateatPa(Lam)shallbe<0.75La.LamisdefinedasthetotalmeasuredcontainmentleakagerateatpressurePa.TestFreuenca~Asetofthreeintegratedleakratetestsshallbeperformedatapproximatelyequalintervalsduringeach10-yearserviceperiod.Thethirdtestofeachsetshallbeconductedinthefinalyearofthe10-yearserviceperiodoroneyearbeforeorafterthefinalyearofthe10-yearserviceperiodprovided:theintervalbetweenanytwoTypeAtestsdoesnotexceedfouryears.i'.3.3.~followingeachin-serviceinspection,thecontainmentairlocks,thesteamgeneratorinspection/maintenancepenetration,andtheequipmenthatchareleaktestedpriortoreturningtheplanttooperation,andanyrepair,replacement,ormodificationofacontainmentbarrierresultingfromtheinserviceinspectionsshallbefollowedbytheappropriateleakagetest.4.4-4Proposed 0
c~shutdownanddepressurizeduntilrepairsareeffectedandthelocalleakagemeetstheacceptancecriterion.Ifitisdeterminedthattheleakagethroughamini-purgesupplyandexhaustlineisgreaterthan0.05Laanengineeringevaluationshallbeperformedandplansforcorrectiveactiondeveloped.4.4.2.4TestFreuenca~Exceptasspecifiedinb.andc.below,individualpenetrationsandcontainmentisolationvalvesshallbetestedduringeachreactorshutdownforrefueling,orotherconvenientintervals,butinnocaseatintervalsgreaterthantwoyears.b.Thecontainmentequipmenthatch,fueltransfertube,steamgeneratorinspection/maintenancepenetration,andshutdownpurgesystemflangesshallbetestedateachrefuelingshutdownoraftereachuse,ifthatbesooner.AmendmentNo.Z84.4-7Proposed c~Thecontainmentairlocksshallbetestedatintervalsofnomorethansixmonthsbypressurizingthespacebetweentheairlockdoors.Inaddition,followingopeningoftheairlockdoor-duringtheinterval,atestshallbeperformedbypressurizingbetweenthedualsealsofeachdooropened,within48hoursoftheopening,unlessthereactorwasinthecoldshutdownconditionatthetimeoftheopeningorhasbeensubsequentlybroughttothecoldshutdowncondition.Atestshallalsobeperformedbypressurizingbetweenthedualsealsofeachdoorwithin48hoursofleavingthecoldshutdowncondition,unlessthedoorshavenotbeenopensincethelasttestperformedeitherbypressurizingthespacebetweentheairlockdoorsorbypressurizingbetweenthedualdoorseals.AmendmentNo.i84.4-8Proposed
thetendoncontaining6brokenwires)shallbeinspected.Theacceptedcriterionthenshallbenomorethan4brokenwiresinanyoftheadditional4tendons.Ifthiscriterionisnotsatisfied,allofthetendonsshallbeinspectedandifmorethan5%ofthetotalwiresarebroken,thereactorshallbeshut,downanddepressurized.4.4.4.2Pre-StressConfirmationTest'a~Lift-offtestsshallbeperformedonthe14tendonsidentifiedin4.4.4.1aabove,attheintervalsspecifiedin4.4.4.1b.Iftheaveragestressinthe14tendonscheckedislessthan144,000psi(60%ofultimatestress),alltendonsshallbecheckedforstressandretensioned,ifnecessary,toastressof144,000psi.b.Beforereseatingatendon,additionalstress(6%)shallbeimposedtoverifytheabilityofthetendontosustaintheaddedstressappliedduringaccidentconditions.4.4.54.4.5.1ContainmentIsolationValvesEachcontainmentisolationvalveshallbedemonstratedtobeOPERABLEinaccordancewiththeGinnaStationPumpandValveTestprogramsubmittedinaccordancewith10CFR50.55a.4.4.64.4.6.1ContainmentIsolationResonseEachcontainmentisolationinstrumentationchannelshallbedemonstratedOPERABLEbytheperformanceoftheCHANNELCHECK,CHANNELCALIBRATION,andCHANNELFUNCTIONALTESToperationsfortheMODESandatthefrequenciesshowninTable4.1-1.4.4.6.2Theresponsetimeofeachcontainmentisolationvalveshallbedemonstratedtobewithinitslimitat,leastonceper18months.Theresponsetimeincludesonlythevalvetraveltimeforthosevalveswhichthesafetyanalysisassumptionstakecreditforachangeinvalvepositioninresponsetoacontainmentisolationsignal.AmendmentNo.Zf4.4-11Proposed
ATTACHMENTBThepurposeofthisamendmentistoremoveTable3.6-1,"ContainmentIsolationValves",fromtheR.E.GinnaTechnicalSpecifications.ThereferencetoTable3.6-1inTechnicalSpecificationsections3.6.3.1,4.4.5.1,and4.4.6.2willbedeleted.AreferencetoUFSARTable6.2-13willbeprovidedintheBasisforTechnicalSpecification3.6.Inaddition,theinoperabilitydefinitionandactionrequiredstatementforTechnicalSpecification3.6.3.1willbeclarified.TechnicalSpecifications4.4.1.5,sectiona(ii)and4.4.2.4,sectionb,willberevisedtoincludethemodifiedsteamgeneratorinspection/maintenancepenetration.TechnicalSpecification4.4.1.5,sectiona(ii)willalsobeclarified.Thetemporarynotesassociatedwiththepurgesystemandmini-purgevalves(TechnicalSpecifications3.6.5,4.4.2.4sectiona,and4.4.2.4sectiond)willberemovedsincethevalveshavebeeninstalled.Also,theacceptancecriteriaforcontainmentleakagecriteriainTechnicalSpecification4.4.1.4willbeclarified.The1988InserviceTest(IST)ProgramprovidedacompletereviewoftheGinnaContainment,IsolationValvesandtheirtestingrequirements.TheinformationobtainedduringthisreviewwassubmittedtotheNRCtodefinetheISTrequirementsforthethirdten-yearintervalatGinna.ThissubmittalwassubsequentlyapprovedbytheNRC.Asaresultofthissubmittalandapproval,numerousclarificationswererequiredofTechnicalSpecificationTable3.6-1andUFSARTable6.2-13.However,thisamendmentwillremoveTechnicalSpecificationTable3.6-1.ThenecessarychangestoUFSARTable6.2-13havebeencompleted.AttachmentCcontainsthesafetyevaluationrelatedtothesechangesforyourinformation.TheremovalofTable3.6-1fromtheTechnicalSpecificationsandtheincorporationoftherequiredinformationintoGinnaUFSARTable6.2-13willkeepthelistingoftheContainmentIsolationValveswithinalicenseecontrolleddocument.Changestothisdocumentcanonlybeperformedunderthecriteriaof10CFR50.59toensurethatnounreviewedsafetyquestionsarerelatedtothechange.AnyadditionalchangestoUFSARTable6.2-13willbesubmittedaspartoftheannualUFSARupdate.Inaddition,areportsummaryofthechangestotheGinnaUFSARarefurnishedtotheNRConanannualbasis.AreferencetoGinnaUFSARTable6.2-13isnowprovidedintheBasisforTechnicalSpecification3.6consistentwithStandardTechnicalSpecifications.Theadditionofthesteamgeneratorinspection/maintenancepenetrationtoboththeUFSARTableandthenecessaryTechnicalSpecificationsurveillancerequirementsistheresultofamodificationtoenhancecontainmentclosureduringmid-loopoperation(GenericLetter88-17).Nonewcontainmentisolationvalveswereaddedasaresultofthismodification.TheadditionofthispenetrationtotheUFSARTableandTechnicalSpecifications4.4.1.5,sectiona(ii)and4.4.2.4,sectionb,causesthenewpenetrationtobetreatedconsistentwithrespecttothePersonnelandEquipmentHatches,andthefueltransfertube(seeletterfromR.C.Mecredy,RGGE,toA.R.Johnson,NRC,datedMarch13,1990).
ThefirstlineofTechnicalSpecification4.4.1.5,sectiona(ii)willalsobemodifiedtostate"followingeachin-serviceinspection..."Thehyphenationof"in-service"istocorrectatypographicalerroronly.Thereplacementof"one"with"each"providesgreaterunderstandingofthetestfrequencyrequirements.Thesechangesareaminorclarificationonlyanddonotinvolveatechnicalchange.ThechangesrelatedtotheinoperabilitydefinitionforcontainmentisolationvalvesinTechnicalSpecification3.6.3.1donotinvolveanytechnicalchanges.Instead,theseclarificationswillprovideconsistencywith10CFR50AppendixJrequirements.ChangeswithrespecttotherequiredactionsofTechnicalSpecification3.6.3.1allowconsistencywithStandardTechnicalSpecifications.However,"isolationboundary"wasusedinplaceof"isolationvalve"sincenotallpenetrationshavetwocontainmentisolationvalvesinplace.Forexample,penetrationsunderthespecificationsforGeneralDesignCriteria57onlyrequireasingleisolationvalve;thepipingprovidesanadditionalboundary.Theuseof"isolationboundary"isaalsoconsistentwiththecolumnheadingsofthecurrentContainment.IsolationValveTable3.6-1.Informationonwhat,qualifiesasan"isolationboundary"isprovidedintheBasisforTechnicalSpecification3.6.ThesecriteriaareconsistentwiththenecessaryGeneralDesignCriteriaorexemptionasappropriate.ThechangeswithrespecttocontainmentleakagecriteriainTechnicalSpecification4.4.1.4areclarificationsonly.AlltermscontainedinthedefinitionforLtwillbespecifiedintheTechnicalSpecificationsconsistent.with10CFR50AppendixJ.Thetemporarynotesassociatedwiththepurgeandmini-purgevalvesinTechnicalSpecifications3.6.5,4.4.2.4sectiona,and4.4.2.4sectiondwillberemovedsincethesevalveshavebeeninstalled.Thisisnotatechnicalchangesincethenoteswereonlyintendedtobeapplicableuntilthecompletionofthenecessarymodifications.Inaccordancewith10CFR50.91,thesechangestotheTechnicalSpecificationshavebeenevaluatedtodetermineiftheoperationofthefacilityinaccordancewiththeproposedamendmentwould:involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated;or2.createthepossibilityofanewordifferentkindofaccident,previouslyevaluated;or3.involveasignificantreductioninamarginofsafety.Theseproposedchangesdonotincreasetheprobabilityorconsequencesofapreviouslyevaluatedaccidentorcreateanewordifferenttypeofaccident.Furthermore,thereisnoreductioninthemarginofsafetyforanyparticularTechnicalSpecification.ThedetailedchangesaredescribedinTable1.
Therefore,RochesterGasandElectricsubmitsthattheissuesassociatedwiththisAmendmentrequestareoutsidethecriteriaoflOCFR50.91;andanosignificanthazardsfindingiswarranted.
AttachmentC(UFSARChangesSafetyEvaluation)