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| {{#Wiki_filter:ACCELERATEDRIDSPROCESSING)REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9410170196DOC.DATE:94/10/07NOTARIZED:NODOCKETIFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONPFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndiana&MichiganEleRECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)R | | {{#Wiki_filter:ACCELERATED RIDSPROCESSING) |
| | REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9410170196 DOC.DATE: |
| | 94/10/07NOTARIZED: |
| | NODOCKETIFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION PFITZPATRICK,E. |
| | IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)R |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ApplicationforamendstolicensesDPR-586DPR-74,requestchangerereactorcoolantsystempressureisolationvalves.DISTRIBUTIONCODE:AOOIDCOPIESRECEIVED:LTRIENCLgSIZE:ITITLE:ORSubmittal:GeneralDistributionNOTESRECIPIENTIDCODE/NAMEPD3-1LAHICKMAN,JINTERN:%LE,CENTZRNRR/DRCH/HICBNRR/DSSA/SPLBNUDOCS-ABSTRACTEXTERNAL:NOACCOPIESLTTRENCL111111111111RECIPIENTIDCODE/NAMEPD3-1PDNRR/DE/EELBNRR/DRPWNRR/DSSA/SRXBOGC/HDS2NRCPDRCOPIESLTTRENCL111111111011DUNNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEiVASTE!CONTACTTHEDOCUifENTCONTROLDESK,ROO!vIPl-37(EXT.504-2083)TOELINIINATEYOURMAML'ROD!DISTRIBUTIONLISTSI'ORDOCUMENTSYOUDON"I'L'ED!TOTALNUMBEROFCOPIESREQUIRED:LTTR13ENCL12 JE)III indianaMichiganPowerCompanyP.O.8ox16631Cofumbus,OH43216AEP:NRC:1180ADonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74ADDITIONALINFORMATIONFORTECHNICALSPECIFICATIONCHANGEREQUESTREACTORCOOLANTSYSTEMPRESSUREISOLATIONVALVESU.S.NuclearRegulatoryCommissionDocumentControlDeskWashington,DC20555Attn:W.T.RussellOctober7,1994
| | Application foramendstolicensesDPR-586DPR-74,request changerereactorcoolantsystempressureisolation valves.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR IENCLgSIZE:ITITLE:ORSubmittal: |
| | GeneralDistribution NOTESRECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERN:%LE,CENTZRNRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL: |
| | NOACCOPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME PD3-1PDNRR/DE/EELB NRR/DRPWNRR/DSSA/SRXB OGC/HDS2NRCPDRCOPIESLTTRENCL111111111011DUNNOTETOALL"RIDS"RECIPIENTS: |
| | PLEASEHELPUSTOREDUCEiVASTE!CONTACTTHE DOCUifENT CONTROLDESK,ROO!vIPl-37(EXT.504-2083)TOELINIINATEYOURMAML'ROD!DISTRIBUTION LISTSI'ORDOCUMENTS YOUDON"I'L'ED!TOTALNUMBEROFCOPIESREQUIRED: |
| | LTTR13ENCL12 JE)III indianaMichiganPowerCompanyP.O.8ox16631Cofumbus, OH43216AEP:NRC:1180A DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74ADDITIONAL INFORMATION FORTECHNICAL SPECIFICATION CHANGEREQUESTREACTORCOOLANTSYSTEMPRESSUREISOLATION VALVESU.S.NuclearRegulatory Commission DocumentControlDeskWashington, DC20555Attn:W.T.RussellOctober7,1994 |
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| ==DearMr.Russell:== | | ==DearMr.Russell:== |
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| ==Reference:== | | ==Reference:== |
| AEP:NRC:1180,TechnicalSpecificationChangeRequest,November15,1993Inaccordwithrequestsfromyourstaff,thisletteranditsattachmentssupplyadditionalinformationtosupportandamendourpreviousapplication,containedinthereferencedletter,foratechnicalspecificationl,'T/S)changeforDonaldC.CookNuclearPlantUnits1and2.Specifically,inthereferencedletterweproposedandsupportedthedeletionoftheoverlyrestrictiveleakagelimitationrequirementsforReactor'oolantSystemPressureIsolationValveslistedinT/STable3.4-0,whilemaintainingthemore,reasonabletestingrequirementsforthesubjectvalvesinaccordancewithASMESectionXI.InconversationsheldonSeptember26,1994,yourstaffindicatedthattherewerenotechnicalconcernswiththesubjectrequest;however,theysuggestedaslightlydifferentapproachtoachievingthesamechange.InsteadofdeletingthesubjecttestingrequirementsfromtheT/Ss,thestaffsuggestedandweagreedtoreplacethecurrentT/StestingrequirementswiththoserequiredbyASMESectionXI.9'410170196941007PDRRDQDK050003i5I.....=..PDR,o( | | |
| Mr.W.T.Russell-2-AEP:NRC:1180AAttachment1tothislettercontainstheadditionalinformationrequestedbyyourstafftosupportthesemodificationstoourT/Ss.Foryourconvenience,allofthepreviouslysuppliedinformationinthereferencedletterhasbeenincludedinthisattachment,withchangesindicatedintherighthandmargintoaddresstheNRC'srequestedapproachasoutlinedabove.TheaffectedT/Spages,markedtoshowproposedrevisions,areincludedinAttachment2.Attachment3containstheaffectedT/Spages,withproposedchangestypedinplace.Webelievethattheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofeffluentsorasignificantincreaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheT/SchangesoriginallyproposedinthereferencedletterwerereviewedbythePlantNuclearSafetyReviewCommitteeandtheNuclearSafetyandDesignReviewCommittee.ThechangestothatsubmittalincludedhereinhavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandwillbereviewedbytheNuclearSafetyandDesignReviewCommitteeatitsnextscheduledmeeting.Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtothe~MichiganPublicServiceCommissionandtotheMichiganDepartmentofPublicHealth.Thisletterissubmittedpursuantto10CFR50.30(b)and,assuchanoathstatementisattached.Sincerely,VicePresidentcadAttachments Mr.W.T.RussellAEP:NRC'1180Acc:A.A.BlindG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector-BridgmanJ.R.Padgett COUNTYOFFRANKLINE.E.Fitzpatrick,beingdulysworn,deposesandsaysthatheistheVicePresidentoflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingTechnicalSpecificationChangeRequestReactorCoolantSystemPressureIsolationValvesandknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledgeandbelief.Subscribedandsworntobeforemethis~4dayof19~%NTARYPUBLCR)TAD.HILLNOTARYPUBLIC.STATEOFOHIO 4il ATTACHMENT1TOAEP'NRC:1180ADESCRIPTIONOFPROPOSEDCHANGESAND10CFR50.92SIGNIFICANTHAZARDSCONSIDERATIONANALYSIS~~ | | AEP:NRC:1180, Technical Specification ChangeRequest,November15,1993Inaccordwithrequestsfromyourstaff,thisletteranditsattachments supplyadditional information tosupportandamendourpreviousapplication, contained inthereferenced letter,foratechnical specification l,'T/S)changeforDonaldC.CookNuclearPlantUnits1and2.Specifically, inthereferenced letterweproposedandsupported thedeletionoftheoverlyrestrictive leakagelimitation requirements forReactor'oolantSystemPressureIsolation ValveslistedinT/STable3.4-0,whilemaintaining themore,reasonable testingrequirements forthesubjectvalvesinaccordance withASMESectionXI.Inconversations heldonSeptember 26,1994,yourstaffindicated thattherewerenotechnical concernswiththesubjectrequest;however,theysuggested aslightlydifferent approachtoachieving thesamechange.Insteadofdeletingthesubjecttestingrequirements fromtheT/Ss,thestaffsuggested andweagreedtoreplacethecurrentT/Stestingrequirements withthoserequiredbyASMESectionXI.9'410170196 941007PDRRDQDK050003i5I.....=..PDR,o( |
| ATTACHMENT1TOAEP:NRC:1180APage1BACKGROUNDTheReactorSafetyStudyWASH-1400/NUREG75/014(Reference,l)analyzeda.so-calledEventVSequenceresultinginanintersystemloss-of-coolantaccident(ISLOCA).ItwasconcludedthattheISLOCAwasasignificantcontributortocoredamagefrequencysincethecontainmentisbypassedandreactorcoolantisreleaseddirectlytotheauxiliarybuilding.Asaresultoftheabovefinding,theUSNRCissuedaletter,"LWRPrimaryCoolantSystemPressureIsolationValves,"datedFebruary25,1980,(Reference2),requestingLWRlicenseestoprovidethefollowinginformation:'DescribethevalveconfigurationatyourplantandindicateifanEventVisolationvalveconfigurationexistswithintheClassIboundaryofthehighpressurepipingconnectionPCSpipingtolowpressuresystempiping;e.g.,(1)twocheckvalvesinseries,or(2)twocheckvalvesinserieswithaMOVI2...,Ifeithero'ftheaboveEventVconfigurationsexistsmt.'yourfaci3.ity,'indicatewhether.;:.continuous'surveillance'r'eqiodictests.are'e'ingaccomplishedonsuchvalvestoensureintegrity.Alsoindicatewhethervalveshavebeenknown,orfound,tolackintegrity;and3.IfeitheroftheaboveEventVconfigurationsexistatyourfacility,indicatewhetherplantproceduresshouldberevisedorifplantmodificationsshouldbemadetoincreas'ereliability.AEPSCrespondedtotheaboveUSNRCletterwithletterAEP:NRC:0371,"ReactorCoolantSystemPressureIsolationValves,"datedMarch24,1980,(Reference3).Inthisletter,theUSNRCwasinformedthatthefollowingvalveconfigurationsareusedatCookNuclearPlant:1)Aminimumofthreecheckvalvesinseries,2)Twocheckvalveswithaminimumofaclosedmotoroperatedvalveinseries, ATTACHMENT1TOAEP:NRC:1180APage23)Twocheckvalveswithaclosedhandoperatedvalveinseries,and/or4)Acheckvalvewithtwoclosedairoperatedvalves.inseries.AEP:NRC:0371concludedthat:"ThereforenoEventVconfigurationexistsattheCookNuclearPlant.Consequently,therequestsinItems2and3ofMr.Eisenhut'sletterarenotapplicabletotheCookNuclearPlant."OnApril20,1981,theUSNRCissuedan"OrderforModificationofLicensesConcerningPrimaryCoolantSystemPressureIsolationValves"forCookNuclearPlant(Reference4).Thisorderstatedthat"WehaveconcludedthataWASH-1400EventVvalveconfigurationexistsatyourfacilityandthatthecorrectiveactionasdefinedintheattachedorderisnecessary."AttachedtotheorderweretheTechnicalEvaluationReport(TER)supportingtheorderandthenewtechnicalspecifications(T/Ss)which,accordingtotheorder,"...willensurepublichealthandsafetyovertheoperatinglifeofyourfacility."ThesenewT/SswereincorporatedatthattimeintotheoperatinglicensesforCookNuclear.Plant.,'h1987,'the'USNRC'.issuedgeneric.,let<br.(GL)'.87-06;"."PeriodicVerific'ationofLeak'TightIntegrityofPressureIsolation'Valves"'(Reference5).InourresponsetothatGL,AEP:NRC:1041(Reference6),westatedthat12-SI-170L2,12-SI-170L3,12-RH-133,and12-RH-134areleaktestedasperthesurveillancerequirementsintheT/Ss.Theproposedchangesinthissubmittal,therefore,modifyourresponsetoGL87-06.Finally,in1992,theUSNRCissuedinformationnotice92-36,"IntersystemLOCAOutsideContainment"(Reference7).Thisinformationnoticelistedeleven"ObservedPlantVulnerabilitiestoISLOCAPrecursors."AreviewofthisinformationnoticeconcludedthattheconcernsraisedareadequatelyaddressedbycontrolscurrentlyinplaceorplannedattheCookNuclearPlant..TheproposedchangestotheT/SswillnotalterthisconclusionbecauseourresponsetotheinformationnoticewasnotbasedonexistingT/Ss.
| | Mr.W.T.Russell-2-AEP:NRC:1180A Attachment 1tothislettercontainstheadditional information requested byyourstafftosupportthesemodifications toourT/Ss.Foryourconvenience, allofthepreviously suppliedinformation inthereferenced letterhasbeenincludedinthisattachment, withchangesindicated intherighthandmargintoaddresstheNRC'srequested approachasoutlinedabove.TheaffectedT/Spages,markedtoshowproposedrevisions, areincludedinAttachment 2.Attachment 3containstheaffectedT/Spages,withproposedchangestypedinplace.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure. |
| ATTACHMENT1TOAEP'NRC'1180APage3COOKNUCLEARPLANTIPEOnMay1,1992,AEPSCrespondedtogenericletter88-20(Reference8),inAEP:NRC:1082E,IndividualPlantExamination(IPE)submittal(Reference9),andprovidedfurtherinformationontheanalysisoftheISLOCAinReference10.(SeetheEnclosure,tothis
| | TheT/Schangesoriginally proposedinthereferenced letterwerereviewedbythePlantNuclearSafetyReviewCommittee andtheNuclearSafetyandDesignReviewCommittee. |
| | Thechangestothatsubmittal includedhereinhavebeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee atitsnextscheduled meeting.Incompliance withtherequirements of10CFR50.91(b)(1), |
| | copiesofthisletteranditsattachments havebeentransmitted tothe~MichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.Thisletterissubmitted pursuantto10CFR50.30(b)and,assuchanoathstatement isattached. |
| | Sincerely, VicePresident cadAttachments Mr.W.T.RussellAEP:NRC'1180A cc:A.A.BlindG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector |
| | -BridgmanJ.R.Padgett COUNTYOFFRANKLINE.E.Fitzpatrick, beingdulysworn,deposesandsaysthatheistheVicePresident oflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingTechnical Specification ChangeRequestReactorCoolantSystemPressureIsolation Valvesandknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledge andbelief.Subscribed andsworntobeforemethis~4dayof19~%NTARYPUBLCR)TAD.HILLNOTARYPUBLIC.STATEOFOHIO 4il ATTACHMENT 1TOAEP'NRC:1180A DESCRIPTION OFPROPOSEDCHANGESAND10CFR50.92 SIGNIFICANT HAZARDSCONSIDERATION ANALYSIS~~ |
| | ATTACHMENT 1TOAEP:NRC:1180A Page1BACKGROUND TheReactorSafetyStudyWASH-1400/NUREG 75/014(Reference,l) analyzeda.so-called EventVSequenceresulting inanintersystem loss-of-coolant accident(ISLOCA). |
| | Itwasconcluded thattheISLOCAwasasignificant contributor tocoredamagefrequency sincethecontainment isbypassedandreactorcoolantisreleaseddirectlytotheauxiliary building. |
| | Asaresultoftheabovefinding,theUSNRCissuedaletter,"LWRPrimaryCoolantSystemPressureIsolation Valves,"datedFebruary25,1980,(Reference 2),requesting LWRlicensees toprovidethefollowing information: |
| | 'Describe thevalveconfiguration atyourplantandindicateifanEventVisolation valveconfiguration existswithintheClassIboundaryofthehighpressurepipingconnection PCSpipingtolowpressuresystempiping;e.g.,(1)twocheckvalvesinseries,or(2)twocheckvalvesinserieswithaMOVI2...,Ifeithero'ftheaboveEventVconfigurations existsmt.'yourfaci3.ity,'indicate whether.;:.continuous |
| | 'surveillance |
| | 'r'eqiodictests.are'e'ingaccomplished onsuchvalvestoensureintegrity. |
| | Alsoindicatewhethervalveshavebeenknown,orfound,tolackintegrity; and3.IfeitheroftheaboveEventVconfigurations existatyourfacility, indicatewhetherplantprocedures shouldberevisedorifplantmodifications shouldbemadetoincreas'e reliability. |
| | AEPSCresponded totheaboveUSNRCletterwithletterAEP:NRC:0371, "ReactorCoolantSystemPressureIsolation Valves,"datedMarch24,1980,(Reference 3).Inthisletter,theUSNRCwasinformedthatthefollowing valveconfigurations areusedatCookNuclearPlant:1)Aminimumofthreecheckvalvesinseries,2)Twocheckvalveswithaminimumofaclosedmotoroperatedvalveinseries, ATTACHMENT 1TOAEP:NRC:1180A Page23)Twocheckvalveswithaclosedhandoperatedvalveinseries,and/or4)Acheckvalvewithtwoclosedairoperatedvalves.inseries.AEP:NRC:0371 concluded that:"Therefore noEventVconfiguration existsattheCookNuclearPlant.Consequently, therequestsinItems2and3ofMr.Eisenhut's letterarenotapplicable totheCookNuclearPlant."OnApril20,1981,theUSNRCissuedan"OrderforModification ofLicensesConcerning PrimaryCoolantSystemPressureIsolation Valves"forCookNuclearPlant(Reference 4).Thisorderstatedthat"Wehaveconcluded thataWASH-1400 EventVvalveconfiguration existsatyourfacilityandthatthecorrective actionasdefinedintheattachedorderisnecessary." |
| | AttachedtotheorderweretheTechnical Evaluation Report(TER)supporting theorderandthenewtechnical specifications (T/Ss)which,according totheorder,"...willensurepublichealthandsafetyovertheoperating lifeofyourfacility." |
| | ThesenewT/Sswereincorporated atthattimeintotheoperating licensesforCookNuclear.Plant.,'h1987,'the'USNRC'.issued generic.,let<br.(GL)'.87-06; |
| | "."Periodic Verific'ation ofLeak'TightIntegrity ofPressureIsolation |
| | 'Valves"'(Reference 5).InourresponsetothatGL,AEP:NRC:1041 (Reference 6),westatedthat12-SI-170L2, 12-SI-170L3, 12-RH-133, and12-RH-134 areleaktestedasperthesurveillance requirements intheT/Ss.Theproposedchangesinthissubmittal, therefore, modifyourresponsetoGL87-06.Finally,in1992,theUSNRCissuedinformation notice92-36,"Intersystem LOCAOutsideContainment" (Reference 7).Thisinformation noticelistedeleven"Observed PlantVulnerabilities toISLOCAPrecursors." |
| | Areviewofthisinformation noticeconcluded thattheconcernsraisedareadequately addressed bycontrolscurrently inplaceorplannedattheCookNuclearPlant..TheproposedchangestotheT/Sswillnotalterthisconclusion becauseourresponsetotheinformation noticewasnotbasedonexistingT/Ss. |
| | ATTACHMENT 1TOAEP'NRC'1180A Page3COOKNUCLEARPLANTIPEOnMay1,1992,AEPSCresponded togenericletter88-20(Reference 8),inAEP:NRC:1082E, Individual PlantExamination (IPE)submittal (Reference 9),andprovidedfurtherinformation ontheanalysisoftheISLOCAinReference 10.(SeetheEnclosure, tothis |
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| ==Attachment:== | | ==Attachment:== |
| DonaldC.CookNuclearPlant,PathsConsideredasPossibleEventV-SequenceLOCA,takenfromReference10).InthedeterminationoftheISLOCAinitiatingeventfrequency,leaktestingof12-SI-170L2,12-SI-170L3,12-RH-133,and12-RH-134,asrequiredbythesurveillancerequirementsintheT/Ss,wasaddressed.TheIPEforCookNuclearPlantconcludedthattheISLOCAwastheaccidentthatcontributedtheleasttotheoverallcoredamagefrequency.ThecalculatedISLOCAinitiatingeventfrequencywasapproximately6.70E-07,andthecalculatedprobabilityofISLOCAcoredamagewasapproximately5.4E-08.ThecontributiontooverallcoredamagefrequencyfromanISLOCAislessthan0.1%ofthe6.26E-05IPEcalculatedcoredamagefrequencyperreactoryear.Itisseen,therefore,thatthecontributionfromanISLOCAeventatCookNuclearPlantisnegligible.ACOMPARISON.OFWASH1400VSCOOKCLEARPLANTWITH.RESPECT'~TOXSOOATheISLOCA.accidentisde'scribedinSection5.3.2.5ofWASH.-1400,andthequantificationofitscoredamagefrequency,isSoundinAppendixV,Section4.4ofWASH-1400.ThecoredamagefrequencycalculatedinWASH-1400is4.00E-06/reactoryear.WASH-1400evaluatedthreepathwaysoftwocheckvalvesinseries,andassumedthatthe600psiLowPressureInjectionSystem(LPIS),onceexposedtoRCSpressure,wouldfailandcreateapproximatelya6"effectivediameterLOCA.Nootheraccidentinitiationfeaturesormitigatingactionsweremodeled.IntheCookNuclearPlantIPE,ninedifferentpathwaysforanISLOCAeventwereanalyzed.Thesepathways(seeEnclosuretothisAttachment),consistedofeitherthreecheckvalvesinseries,twocheckvalvesandaclosedmotoroperatedvalve(MOV)inseries,ortwonormallyclosedMOVsinseries.AlthoughWASH-1400lookedatcheckvalveleaktestingasasensitivityanalysis,theCookNuclearPlantIPEaccountedforthein-placeleaktestingwhen'alculatingtheprobabilityofanISLOCAoccurring.Inaddition,theCookNuclearPlantIPEmodeledmitigatingactionsfortheISLOCAeventintheeventtree.The ATTACHMENT1TOAEP:NRC:1180APage4.lowpressureinjectionsystempipingwasreviewed,andfoundtobecapableofwithstandingthefullpressureofthereactorcoolantsystem.Onlyhoopstresseswerefoundtobesignificant,sinceafterinitiationofanISLOCAtheheatuprateofthepipingwouldberelativelyslow,minimizingthermalstresses.Thus,isolationoftheLOCApathwayandpotentiallysuccessfulmitigatingactivitiesarepossible.TheIPEISLOCAinitiatingeventfrequencywasapproximatelyanorderofmagnitudelowerthantheWASH-1400coredamagefrequency(4.00E-06),andtheIPEISLOCAcoredamagefrequencyvaluewasapproximatelytwoordersofmagnitudelowerthantheWASH-1400values.Finally,toaddresstheimpactofremovingtheT/Srequirementsandonlytesting12-SI-170L2,12-SI-170L3,12-RH-133,and12-RH-134atarefuelingoutagefrequency,asensitivityrunwasmadeinsupportofthissubmittal.Sincetheinserviceinspectionprogramwilldiscoverarupturedvalve,theadditionalT/Srequirementwasonlycreditedwiththeabilitytoidentifyastuckopenvalve.Thiscreditwasremovedforthissensitivityrun.ItwasfoundthattheISLOCAinitiatingeventfrequency,andISLOCAprobabilityofcoredamagewouldalsoincreaseby5.4%tothemid5.00E-08range,andtheoverallcoredamagefrequencywouldremainunchanged.Thus,theproposedT/Swillessentially'rovideprotectionequivalenttotheexistingT/SfromanISLOCA.ISTPROGRAMThesubjectcheckvalvesofthissubmittalarecurrentlybeingtestedinMode5,ColdShutdown,asrequiredbytheT/SssurveillancerequirementspriortogoingtoMode4,HotShutdown.Theallowableleakratecannotexceed1gpm.IftheT/Ssaremodifiedasrequested,thesevalveswouldcontinuetobetestedundertheISTProgram(ASMEBoilerandPressureVesselCode,SectionXI),onarefuelingoutagefrequency,liketheirsistervalvesint'eotherloops'intheResidualHeatRemovalSystem.TheacceptancecriteriafortheleaktestingofthesevalvesundertheISTProgramhasbeendefinedhereas0.5gpmpernominalinchofvalvesize,consistentwithNUREG-1431(Reference12).
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| ATTACHMENT1TOAEP:NRC:1180APage5DESCRIPTIONOFPROPOSEDTECHNICALSPECIFICATIONCHANGESTheproposedchangesarelistedbelow.Theyareidenticalforbothunits.1~PT/S3.4.6.2f.Replaceinitsentirety.2.T/S3.4.6.2APPLICABILITY:Delete"**"andreplacewitha"*"3.T/S3.4.6.2ACTIONc.Delete"exceptwhen...by50$ormore."T/S3.4.6.2ACTIONc,footnote*.Deletethefootnote.5.T/S3.4'.2APPLICABILITY,footnote**.ChangetheIt'lltoII*II6.T/S4.4.6.2.2.Replaceitwiththefollowingtext:"Eachreactor'oolantsystempressure.isolationvalvespecifiedinTable3..4-.0'shallbe.,'demonstrate@'OPERABLE'pursuant.to..'Sp'ecification4:05."7.T/S3/4.6.2,Table3.4-0.ReplacetheTableinitsentirety.10CFR502SIGNIFICANTHAZARDSCONSIDERATIONANALYSISPer10CFR50.92,aproposedamendmenttoanoperatinglicensewillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentsatisfiesthefollowingthreecriteria:1)Doesnotinvolveasignificantincreaseintheprobabilityorconsequencesofan.accidentpreviouslyanalyzed,2)doesnotcreatethepossibilityofanewordifferentkindofaccidentfromanaccidentpreviouslyanalyzedorevaluated,or3)doesnotinvolveasignificantreductioninamarginofsafety.
| | DonaldC.CookNuclearPlant,PathsConsidered asPossibleEventV-Sequence LOCA,takenfromReference 10).Inthedetermination oftheISLOCAinitiating eventfrequency, leaktestingof12-SI-170L2, 12-SI-170L3, 12-RH-133, and12-RH-134, asrequiredbythesurveillance requirements intheT/Ss,wasaddressed. |
| ATTACHMENT1TOAEP:NRC:1180APage6Criterion1TheISLOCAisnotoneoftheaccidentspreviouslyanalyzedinChapter14,SafetyAnalysis,oftheCookNuclearPlantUpdatedFinalSafetyAnalysisReport.Chapter14analyzesthelargebreakLOCAinSection14.3.1,and"lossofreactorcoolantfromsmallrupturedpipesorfromcracksinlargepipeswhichactuatestheECCS,"orsmallbreakLOCAinSection14.3.2.Therefore,theproposedT/SsmodificationstotheReactorCoolantSystempressureisolationvalvesinTable3.4-0,willnotincreasetheprobabilityortheconsequencesofthelargebreakorthesmallbreakLOCAspreviouslyanalyzedfortheCookNuclearPlant.Criterion2TheReactorCoolantSystempressureisolationvalvesinTable3.4-0oftheT/SswereaddedbecauseWASH-1400identifiedtheISLOCAasasignificantcontributortocoredamagefrequency.TheproposedmodificationsofthesubjectvalvesTechnicalSpecificationsurveillancerequirementstorelyonthetestingrequirementsmandatedbytheIn-ServiceTestingProgramofASMEXIdoesnotcreatethepossibilityofanewordifferentkindofaccidentfromthelargebreakorthesmallbreakLOCAspreviouely.analyzed'or.theCookNuclearPlant.,I~''riterfon3TheproposedmodificationstotheReactorCoolantSystempressureisolationvalvestestingrequirementsinTable3.4-0oftheT/Ss,willresultinthesevalvesonlybeingtestedonarefuelingoutagefrequencyaspartoftheASMEB6PVCodeSectionXIISTProgram.ThissomewhatreducedtestingfrequencywillresultinaslightincreaseintheISLOCAinitiatingeventfrequency,andISLOCAcontributiontocoredamagefrequencyby5.4%,fromlower5.00E-08/reactoryeartomid5.00E-08/reactoryear.Thisinsignificantincreasewillnotaffecttheoverallcoredamagefrequencyof6.26E-05/reactoryear.Therefore,itisconcludedthattheproposedchangestotheT/SrequirementsfortheReactorCoolantSystempressureisolationvalvesinTable3.4-0,willnotresultinasignificantreductioninthemarginofsafetythatexistsatCookNuclearPlanttopreventanISLOCAortomitigatetheconsequencesofanISLOCA.
| | TheIPEforCookNuclearPlantconcluded thattheISLOCAwastheaccidentthatcontributed theleasttotheoverallcoredamagefrequency. |
| ATTACHMENT1TOAEP:NRC:1180APage7REFERENCESWASH-1400/NUREG75/014,ReactorSafetyStudy:AnAssessmentofAccidentRisksinU.S.CommercialNuclearPlants,USNRC,October1975.2.USNRCLettertoallLWRLicensees:LWRPrimaryCoolantSystemPressureIsolationValves,February25,1980.3.AEP:NRC:0371,ReactorCoolantSystemPressureIsolationValves,March24,1980.4.Letter,S.A.Varga,USNRCtoJ.Dolan,IndianaandMichiganElectricCompany,OrderforModificationofLicensesConcerningPrimaryCoolantSystemPressureIsolationValves,April20,1981.5.USNRCGenericLetter(GL)87-06,"PeriodicVerificationofLeakTightIntegrityofPressureIsolationValves,"March13,1987.6.7..AEP:NRC:1041,GenericLetter87-06,PeriodicVerification'of'LeakTight'Integrityof"PressureIsolationValves>..November12,3.987,'X~USNRCInformationNotice92-36,."IntersystemLOCAOutsideContainment,"May,7,1992.8.InitiationoftheIndividualPlantExaminationforSevereAccidentVulnerabilities-10CFR50.54(f),GenericLetterNo.'8-20,November23,1988.9.AEP:NRC:1082E,IndividualPlantExaminationSubmittal,ResponsetoGenericLetter88-20,May1,1992.10.AEP:NRC:1082F,IndividualPlantExaminationResponsetoNRCQuestions,.February24,1993.AEP:NRC:1180,TechnicalSpecificationChangeRequest,ReactorCoolantSystemPressureIsolationValves,November15,1993.12.NUREG-1431,StandardTechnicalSpecificationsforWestinghousePlants,September1992.
| | Thecalculated ISLOCAinitiating eventfrequency wasapproximately 6.70E-07, andthecalculated probability ofISLOCAcoredamagewasapproximately 5.4E-08.Thecontribution tooverallcoredamagefrequency fromanISLOCAislessthan0.1%ofthe6.26E-05IPEcalculated coredamagefrequency perreactoryear.Itisseen,therefore, thatthecontribution fromanISLOCAeventatCookNuclearPlantisnegligible. |
| ATTACHMENT2TOAEP:NRC:1180AMARKED-UPTECHNICALSPECIFICATIONPAGES}}
| | ACOMPARISON. |
| | OFWASH1400VSCOOKCLEARPLANTWITH.RESPECT |
| | '~TOXSOOATheISLOCA.accident isde'scribed inSection5.3.2.5ofWASH.-1400, andthequantification ofitscoredamagefrequency, isSoundinAppendixV,Section4.4ofWASH-1400. |
| | Thecoredamagefrequency calculated inWASH-1400 is4.00E-06/reactor year.WASH-1400 evaluated threepathwaysoftwocheckvalvesinseries,andassumedthatthe600psiLowPressureInjection System(LPIS),onceexposedtoRCSpressure, wouldfailandcreateapproximately a6"effective diameterLOCA.Nootheraccidentinitiation featuresormitigating actionsweremodeled.IntheCookNuclearPlantIPE,ninedifferent pathwaysforanISLOCAeventwereanalyzed. |
| | Thesepathways(seeEnclosure tothisAttachment), |
| | consisted ofeitherthreecheckvalvesinseries,twocheckvalvesandaclosedmotoroperatedvalve(MOV)inseries,ortwonormallyclosedMOVsinseries.AlthoughWASH-1400 lookedatcheckvalveleaktestingasasensitivity |
| | : analysis, theCookNuclearPlantIPEaccounted forthein-placeleaktestingwhen'alculating theprobability ofanISLOCAoccurring. |
| | Inaddition, theCookNuclearPlantIPEmodeledmitigating actionsfortheISLOCAeventintheeventtree.The ATTACHMENT 1TOAEP:NRC:1180A Page4.lowpressureinjection systempipingwasreviewed, andfoundtobecapableofwithstanding thefullpressureofthereactorcoolantsystem.Onlyhoopstresseswerefoundtobesignificant, sinceafterinitiation ofanISLOCAtheheatuprateofthepipingwouldberelatively slow,minimizing thermalstresses. |
| | Thus,isolation oftheLOCApathwayandpotentially successful mitigating activities arepossible. |
| | TheIPEISLOCAinitiating eventfrequency wasapproximately anorderofmagnitude lowerthantheWASH-1400 coredamagefrequency (4.00E-06), |
| | andtheIPEISLOCAcoredamagefrequency valuewasapproximately twoordersofmagnitude lowerthantheWASH-1400 values.Finally,toaddresstheimpactofremovingtheT/Srequirements andonlytesting12-SI-170L2, 12-SI-170L3, 12-RH-133, and12-RH-134 atarefueling outagefrequency, asensitivity runwasmadeinsupportofthissubmittal. |
| | Sincetheinservice inspection programwilldiscoverarupturedvalve,theadditional T/Srequirement wasonlycreditedwiththeabilitytoidentifyastuckopenvalve.Thiscreditwasremovedforthissensitivity run.ItwasfoundthattheISLOCAinitiating eventfrequency, andISLOCAprobability ofcoredamagewouldalsoincreaseby5.4%tothemid5.00E-08range,andtheoverallcoredamagefrequency wouldremainunchanged. |
| | Thus,theproposedT/Swillessentially |
| | 'rovideprotection equivalent totheexistingT/SfromanISLOCA.ISTPROGRAMThesubjectcheckvalvesofthissubmittal arecurrently beingtestedinMode5,ColdShutdown, asrequiredbytheT/Sssurveillance requirements priortogoingtoMode4,HotShutdown. |
| | Theallowable leakratecannotexceed1gpm.IftheT/Ssaremodifiedasrequested, thesevalveswouldcontinuetobetestedundertheISTProgram(ASMEBoilerandPressureVesselCode,SectionXI),onarefueling outagefrequency, liketheirsistervalvesint'eotherloops'intheResidualHeatRemovalSystem.Theacceptance criteriafortheleaktestingofthesevalvesundertheISTProgramhasbeendefinedhereas0.5gpmpernominalinchofvalvesize,consistent withNUREG-1431 (Reference 12). |
| | |
| | ATTACHMENT 1TOAEP:NRC:1180A Page5DESCRIPTION OFPROPOSEDTECHNICAL SPECIFICATION CHANGESTheproposedchangesarelistedbelow.Theyareidentical forbothunits.1~PT/S3.4.6.2f.Replaceinitsentirety. |
| | 2.T/S3.4.6.2APPLICABILITY: |
| | Delete"**"andreplacewitha"*"3.T/S3.4.6.2ACTIONc.Delete"exceptwhen...by50$ormore."T/S3.4.6.2ACTIONc,footnote*.Deletethefootnote. |
| | 5.T/S3.4'.2APPLICABILITY, footnote**.ChangetheIt'lltoII*II6.T/S4.4.6.2.2. |
| | Replaceitwiththefollowing text:"Eachreactor'oolantsystempressure.isolation valvespecified inTable3..4-.0'shallbe.,'demonstrate@' |
| | OPERABLE'pursuant |
| | .to..'Sp'ecification 4:05."7.T/S3/4.6.2,Table3.4-0.ReplacetheTableinitsentirety. |
| | 10CFR502SIGNIFICANT HAZARDSCONSIDERATION ANALYSISPer10CFR50.92,aproposedamendment toanoperating licensewillnotinvolveasignificant hazardsconsideration iftheproposedamendment satisfies thefollowing threecriteria: |
| | 1)Doesnotinvolveasignificant increaseintheprobability orconsequences ofan.accidentpreviously |
| | : analyzed, 2)doesnotcreatethepossibility ofanewordifferent kindofaccidentfromanaccidentpreviously analyzedorevaluated, or3)doesnotinvolveasignificant reduction inamarginofsafety. |
| | ATTACHMENT 1TOAEP:NRC:1180A Page6Criterion 1TheISLOCAisnotoneoftheaccidents previously analyzedinChapter14,SafetyAnalysis, oftheCookNuclearPlantUpdatedFinalSafetyAnalysisReport.Chapter14analyzesthelargebreakLOCAinSection14.3.1,and"lossofreactorcoolantfromsmallrupturedpipesorfromcracksinlargepipeswhichactuatestheECCS,"orsmallbreakLOCAinSection14.3.2.Therefore, theproposedT/Ssmodifications totheReactorCoolantSystempressureisolation valvesinTable3.4-0,willnotincreasetheprobability ortheconsequences ofthelargebreakorthesmallbreakLOCAspreviously analyzedfortheCookNuclearPlant.Criterion 2TheReactorCoolantSystempressureisolation valvesinTable3.4-0oftheT/SswereaddedbecauseWASH-1400 identified theISLOCAasasignificant contributor tocoredamagefrequency. |
| | Theproposedmodifications ofthesubjectvalvesTechnical Specification surveillance requirements torelyonthetestingrequirements mandatedbytheIn-Service TestingProgramofASMEXIdoesnotcreatethepossibility ofanewordifferent kindofaccidentfromthelargebreakorthesmallbreakLOCAspreviouely |
| | .analyzed'or. |
| | theCookNuclearPlant.,I~''riterfon 3Theproposedmodifications totheReactorCoolantSystempressureisolation valvestestingrequirements inTable3.4-0oftheT/Ss,willresultinthesevalvesonlybeingtestedonarefueling outagefrequency aspartoftheASMEB6PVCodeSectionXIISTProgram.Thissomewhatreducedtestingfrequency willresultinaslightincreaseintheISLOCAinitiating eventfrequency, andISLOCAcontribution tocoredamagefrequency by5.4%,fromlower5.00E-08/reactor yeartomid5.00E-08/reactor year.Thisinsignificant increasewillnotaffecttheoverallcoredamagefrequency of6.26E-05/reactor year.Therefore, itisconcluded thattheproposedchangestotheT/Srequirements fortheReactorCoolantSystempressureisolation valvesinTable3.4-0,willnotresultinasignificant reduction inthemarginofsafetythatexistsatCookNuclearPlanttopreventanISLOCAortomitigatetheconsequences ofanISLOCA. |
| | ATTACHMENT 1TOAEP:NRC:1180A Page7REFERENCES WASH-1400/NUREG 75/014,ReactorSafetyStudy:AnAssessment ofAccidentRisksinU.S.Commercial NuclearPlants,USNRC,October1975.2.USNRCLettertoallLWRLicensees: |
| | LWRPrimaryCoolantSystemPressureIsolation Valves,February25,1980.3.AEP:NRC:0371, ReactorCoolantSystemPressureIsolation Valves,March24,1980.4.Letter,S.A.Varga,USNRCtoJ.Dolan,IndianaandMichiganElectricCompany,OrderforModification ofLicensesConcerning PrimaryCoolantSystemPressureIsolation Valves,April20,1981.5.USNRCGenericLetter(GL)87-06,"PeriodicVerification ofLeakTightIntegrity ofPressureIsolation Valves,"March13,1987.6.7..AEP:NRC:1041, GenericLetter87-06,PeriodicVerification |
| | 'of'LeakTight'Integrity of"Pressure Isolation Valves>..November 12,3.987,'X~USNRCInformation Notice92-36,."Intersystem LOCAOutsideContainment," |
| | May,7,1992.8.Initiation oftheIndividual PlantExamination forSevereAccidentVulnerabilities |
| | -10CFR50.54(f), |
| | GenericLetterNo.'8-20, November23,1988.9.AEP:NRC:1082E, Individual PlantExamination Submittal, ResponsetoGenericLetter88-20,May1,1992.10.AEP:NRC:1082F, Individual PlantExamination ResponsetoNRCQuestions, |
| | .February 24,1993.AEP:NRC:1180, Technical Specification ChangeRequest,ReactorCoolantSystemPressureIsolation Valves,November15,1993.12.NUREG-1431, StandardTechnical Specifications forWestinghouse Plants,September 1992. |
| | ATTACHMENT 2TOAEP:NRC:1180A MARKED-UP TECHNICAL SPECIFICATION PAGES}} |
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Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses
ML17335A2631998-10-0808 October 1998
Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp
ML17335A2761998-10-0808 October 1998
Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required
ML17335A2671998-10-0808 October 1998
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled
ML17335A2311998-09-14014 September 1998
Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm
ML17335A1901998-08-28028 August 1998
Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs
ML17334A7471998-06-10010 June 1998
Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change
ML17334B7011998-03-0303 March 1998
Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases
ML17334B6561997-10-0808 October 1997
Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl
ML17333B0431997-09-19019 September 1997
Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
ML17333A9831997-08-11011 August 1997
Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
ML17335A2101997-08-0101 August 1997
Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS
ML17333A8281997-03-26026 March 1997
Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions
ML17333A8311997-03-26026 March 1997
Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted
ML17333A7121996-12-20020 December 1996
Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency
ML17334B5941996-07-11011 July 1996
Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl
ML17334B5901996-06-19019 June 1996
Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking.
ML17334B5891996-06-11011 June 1996
Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05
ML17333A4201996-04-0808 April 1996
Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1
ML17333A3551996-03-12012 March 1996
Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5
ML17334B5751996-02-29029 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl
ML17334B5741996-02-26026 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks
ML17333A3201996-02-22022 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor
ML17333A3151996-02-22022 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test
ML17333A2641996-01-12012 January 1996
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves
ML17333A2391995-12-19019 December 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B
ML17332B0111995-11-10010 November 1995
Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations
ML17332A9971995-10-20020 October 1995
Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV
ML17332A9111995-08-0606 August 1995
Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified
ML17334B5561995-08-0404 August 1995
Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld
ML17332A8271995-06-30030 June 1995
Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1
ML17334B5501995-06-20020 June 1995
License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07
ML17332A7991995-06-15015 June 1995
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H
ML17334B5481995-05-26026 May 1995
Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria
ML17334B5461995-05-26026 May 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08
ML17332A7661995-05-25025 May 1995
Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty
ML17332A7741995-05-25025 May 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1
ML17332A7771995-05-25025 May 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly
1999-09-23
[Table view] |
Text
ACCELERATED RIDSPROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9410170196 DOC.DATE:
94/10/07NOTARIZED:
NODOCKETIFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION PFITZPATRICK,E.
IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)R
SUBJECT:
Application foramendstolicensesDPR-586DPR-74,request changerereactorcoolantsystempressureisolation valves.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR IENCLgSIZE:ITITLE:ORSubmittal:
GeneralDistribution NOTESRECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERN:%LE,CENTZRNRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL:
NOACCOPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME PD3-1PDNRR/DE/EELB NRR/DRPWNRR/DSSA/SRXB OGC/HDS2NRCPDRCOPIESLTTRENCL111111111011DUNNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEiVASTE!CONTACTTHE DOCUifENT CONTROLDESK,ROO!vIPl-37(EXT.504-2083)TOELINIINATEYOURMAML'ROD!DISTRIBUTION LISTSI'ORDOCUMENTS YOUDON"I'L'ED!TOTALNUMBEROFCOPIESREQUIRED:
LTTR13ENCL12 JE)III indianaMichiganPowerCompanyP.O.8ox16631Cofumbus, OH43216AEP:NRC:1180A DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74ADDITIONAL INFORMATION FORTECHNICAL SPECIFICATION CHANGEREQUESTREACTORCOOLANTSYSTEMPRESSUREISOLATION VALVESU.S.NuclearRegulatory Commission DocumentControlDeskWashington, DC20555Attn:W.T.RussellOctober7,1994
DearMr.Russell:
Reference:
AEP:NRC:1180, Technical Specification ChangeRequest,November15,1993Inaccordwithrequestsfromyourstaff,thisletteranditsattachments supplyadditional information tosupportandamendourpreviousapplication, contained inthereferenced letter,foratechnical specification l,'T/S)changeforDonaldC.CookNuclearPlantUnits1and2.Specifically, inthereferenced letterweproposedandsupported thedeletionoftheoverlyrestrictive leakagelimitation requirements forReactor'oolantSystemPressureIsolation ValveslistedinT/STable3.4-0,whilemaintaining themore,reasonable testingrequirements forthesubjectvalvesinaccordance withASMESectionXI.Inconversations heldonSeptember 26,1994,yourstaffindicated thattherewerenotechnical concernswiththesubjectrequest;however,theysuggested aslightlydifferent approachtoachieving thesamechange.Insteadofdeletingthesubjecttestingrequirements fromtheT/Ss,thestaffsuggested andweagreedtoreplacethecurrentT/Stestingrequirements withthoserequiredbyASMESectionXI.9'410170196 941007PDRRDQDK050003i5I.....=..PDR,o(
Mr.W.T.Russell-2-AEP:NRC:1180A Attachment 1tothislettercontainstheadditional information requested byyourstafftosupportthesemodifications toourT/Ss.Foryourconvenience, allofthepreviously suppliedinformation inthereferenced letterhasbeenincludedinthisattachment, withchangesindicated intherighthandmargintoaddresstheNRC'srequested approachasoutlinedabove.TheaffectedT/Spages,markedtoshowproposedrevisions, areincludedinAttachment 2.Attachment 3containstheaffectedT/Spages,withproposedchangestypedinplace.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
TheT/Schangesoriginally proposedinthereferenced letterwerereviewedbythePlantNuclearSafetyReviewCommittee andtheNuclearSafetyandDesignReviewCommittee.
Thechangestothatsubmittal includedhereinhavebeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee atitsnextscheduled meeting.Incompliance withtherequirements of10CFR50.91(b)(1),
copiesofthisletteranditsattachments havebeentransmitted tothe~MichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.Thisletterissubmitted pursuantto10CFR50.30(b)and,assuchanoathstatement isattached.
Sincerely, VicePresident cadAttachments Mr.W.T.RussellAEP:NRC'1180A cc:A.A.BlindG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector
-BridgmanJ.R.Padgett COUNTYOFFRANKLINE.E.Fitzpatrick, beingdulysworn,deposesandsaysthatheistheVicePresident oflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingTechnical Specification ChangeRequestReactorCoolantSystemPressureIsolation Valvesandknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledge andbelief.Subscribed andsworntobeforemethis~4dayof19~%NTARYPUBLCR)TAD.HILLNOTARYPUBLIC.STATEOFOHIO 4il ATTACHMENT 1TOAEP'NRC:1180A DESCRIPTION OFPROPOSEDCHANGESAND10CFR50.92 SIGNIFICANT HAZARDSCONSIDERATION ANALYSIS~~
ATTACHMENT 1TOAEP:NRC:1180A Page1BACKGROUND TheReactorSafetyStudyWASH-1400/NUREG 75/014(Reference,l) analyzeda.so-called EventVSequenceresulting inanintersystem loss-of-coolant accident(ISLOCA).
Itwasconcluded thattheISLOCAwasasignificant contributor tocoredamagefrequency sincethecontainment isbypassedandreactorcoolantisreleaseddirectlytotheauxiliary building.
Asaresultoftheabovefinding,theUSNRCissuedaletter,"LWRPrimaryCoolantSystemPressureIsolation Valves,"datedFebruary25,1980,(Reference 2),requesting LWRlicensees toprovidethefollowing information:
'Describe thevalveconfiguration atyourplantandindicateifanEventVisolation valveconfiguration existswithintheClassIboundaryofthehighpressurepipingconnection PCSpipingtolowpressuresystempiping;e.g.,(1)twocheckvalvesinseries,or(2)twocheckvalvesinserieswithaMOVI2...,Ifeithero'ftheaboveEventVconfigurations existsmt.'yourfaci3.ity,'indicate whether.;:.continuous
'surveillance
'r'eqiodictests.are'e'ingaccomplished onsuchvalvestoensureintegrity.
Alsoindicatewhethervalveshavebeenknown,orfound,tolackintegrity; and3.IfeitheroftheaboveEventVconfigurations existatyourfacility, indicatewhetherplantprocedures shouldberevisedorifplantmodifications shouldbemadetoincreas'e reliability.
AEPSCresponded totheaboveUSNRCletterwithletterAEP:NRC:0371, "ReactorCoolantSystemPressureIsolation Valves,"datedMarch24,1980,(Reference 3).Inthisletter,theUSNRCwasinformedthatthefollowing valveconfigurations areusedatCookNuclearPlant:1)Aminimumofthreecheckvalvesinseries,2)Twocheckvalveswithaminimumofaclosedmotoroperatedvalveinseries, ATTACHMENT 1TOAEP:NRC:1180A Page23)Twocheckvalveswithaclosedhandoperatedvalveinseries,and/or4)Acheckvalvewithtwoclosedairoperatedvalves.inseries.AEP:NRC:0371 concluded that:"Therefore noEventVconfiguration existsattheCookNuclearPlant.Consequently, therequestsinItems2and3ofMr.Eisenhut's letterarenotapplicable totheCookNuclearPlant."OnApril20,1981,theUSNRCissuedan"OrderforModification ofLicensesConcerning PrimaryCoolantSystemPressureIsolation Valves"forCookNuclearPlant(Reference 4).Thisorderstatedthat"Wehaveconcluded thataWASH-1400 EventVvalveconfiguration existsatyourfacilityandthatthecorrective actionasdefinedintheattachedorderisnecessary."
AttachedtotheorderweretheTechnical Evaluation Report(TER)supporting theorderandthenewtechnical specifications (T/Ss)which,according totheorder,"...willensurepublichealthandsafetyovertheoperating lifeofyourfacility."
ThesenewT/Sswereincorporated atthattimeintotheoperating licensesforCookNuclear.Plant.,'h1987,'the'USNRC'.issued generic.,let<br.(GL)'.87-06;
"."Periodic Verific'ation ofLeak'TightIntegrity ofPressureIsolation
'Valves"'(Reference 5).InourresponsetothatGL,AEP:NRC:1041 (Reference 6),westatedthat12-SI-170L2, 12-SI-170L3, 12-RH-133, and12-RH-134 areleaktestedasperthesurveillance requirements intheT/Ss.Theproposedchangesinthissubmittal, therefore, modifyourresponsetoGL87-06.Finally,in1992,theUSNRCissuedinformation notice92-36,"Intersystem LOCAOutsideContainment" (Reference 7).Thisinformation noticelistedeleven"Observed PlantVulnerabilities toISLOCAPrecursors."
Areviewofthisinformation noticeconcluded thattheconcernsraisedareadequately addressed bycontrolscurrently inplaceorplannedattheCookNuclearPlant..TheproposedchangestotheT/Sswillnotalterthisconclusion becauseourresponsetotheinformation noticewasnotbasedonexistingT/Ss.
ATTACHMENT 1TOAEP'NRC'1180A Page3COOKNUCLEARPLANTIPEOnMay1,1992,AEPSCresponded togenericletter88-20(Reference 8),inAEP:NRC:1082E, Individual PlantExamination (IPE)submittal (Reference 9),andprovidedfurtherinformation ontheanalysisoftheISLOCAinReference 10.(SeetheEnclosure, tothis
Attachment:
DonaldC.CookNuclearPlant,PathsConsidered asPossibleEventV-Sequence LOCA,takenfromReference 10).Inthedetermination oftheISLOCAinitiating eventfrequency, leaktestingof12-SI-170L2, 12-SI-170L3, 12-RH-133, and12-RH-134, asrequiredbythesurveillance requirements intheT/Ss,wasaddressed.
TheIPEforCookNuclearPlantconcluded thattheISLOCAwastheaccidentthatcontributed theleasttotheoverallcoredamagefrequency.
Thecalculated ISLOCAinitiating eventfrequency wasapproximately 6.70E-07, andthecalculated probability ofISLOCAcoredamagewasapproximately 5.4E-08.Thecontribution tooverallcoredamagefrequency fromanISLOCAislessthan0.1%ofthe6.26E-05IPEcalculated coredamagefrequency perreactoryear.Itisseen,therefore, thatthecontribution fromanISLOCAeventatCookNuclearPlantisnegligible.
ACOMPARISON.
OFWASH1400VSCOOKCLEARPLANTWITH.RESPECT
'~TOXSOOATheISLOCA.accident isde'scribed inSection5.3.2.5ofWASH.-1400, andthequantification ofitscoredamagefrequency, isSoundinAppendixV,Section4.4ofWASH-1400.
Thecoredamagefrequency calculated inWASH-1400 is4.00E-06/reactor year.WASH-1400 evaluated threepathwaysoftwocheckvalvesinseries,andassumedthatthe600psiLowPressureInjection System(LPIS),onceexposedtoRCSpressure, wouldfailandcreateapproximately a6"effective diameterLOCA.Nootheraccidentinitiation featuresormitigating actionsweremodeled.IntheCookNuclearPlantIPE,ninedifferent pathwaysforanISLOCAeventwereanalyzed.
Thesepathways(seeEnclosure tothisAttachment),
consisted ofeitherthreecheckvalvesinseries,twocheckvalvesandaclosedmotoroperatedvalve(MOV)inseries,ortwonormallyclosedMOVsinseries.AlthoughWASH-1400 lookedatcheckvalveleaktestingasasensitivity
- analysis, theCookNuclearPlantIPEaccounted forthein-placeleaktestingwhen'alculating theprobability ofanISLOCAoccurring.
Inaddition, theCookNuclearPlantIPEmodeledmitigating actionsfortheISLOCAeventintheeventtree.The ATTACHMENT 1TOAEP:NRC:1180A Page4.lowpressureinjection systempipingwasreviewed, andfoundtobecapableofwithstanding thefullpressureofthereactorcoolantsystem.Onlyhoopstresseswerefoundtobesignificant, sinceafterinitiation ofanISLOCAtheheatuprateofthepipingwouldberelatively slow,minimizing thermalstresses.
Thus,isolation oftheLOCApathwayandpotentially successful mitigating activities arepossible.
TheIPEISLOCAinitiating eventfrequency wasapproximately anorderofmagnitude lowerthantheWASH-1400 coredamagefrequency (4.00E-06),
andtheIPEISLOCAcoredamagefrequency valuewasapproximately twoordersofmagnitude lowerthantheWASH-1400 values.Finally,toaddresstheimpactofremovingtheT/Srequirements andonlytesting12-SI-170L2, 12-SI-170L3, 12-RH-133, and12-RH-134 atarefueling outagefrequency, asensitivity runwasmadeinsupportofthissubmittal.
Sincetheinservice inspection programwilldiscoverarupturedvalve,theadditional T/Srequirement wasonlycreditedwiththeabilitytoidentifyastuckopenvalve.Thiscreditwasremovedforthissensitivity run.ItwasfoundthattheISLOCAinitiating eventfrequency, andISLOCAprobability ofcoredamagewouldalsoincreaseby5.4%tothemid5.00E-08range,andtheoverallcoredamagefrequency wouldremainunchanged.
Thus,theproposedT/Swillessentially
'rovideprotection equivalent totheexistingT/SfromanISLOCA.ISTPROGRAMThesubjectcheckvalvesofthissubmittal arecurrently beingtestedinMode5,ColdShutdown, asrequiredbytheT/Sssurveillance requirements priortogoingtoMode4,HotShutdown.
Theallowable leakratecannotexceed1gpm.IftheT/Ssaremodifiedasrequested, thesevalveswouldcontinuetobetestedundertheISTProgram(ASMEBoilerandPressureVesselCode,SectionXI),onarefueling outagefrequency, liketheirsistervalvesint'eotherloops'intheResidualHeatRemovalSystem.Theacceptance criteriafortheleaktestingofthesevalvesundertheISTProgramhasbeendefinedhereas0.5gpmpernominalinchofvalvesize,consistent withNUREG-1431 (Reference 12).
ATTACHMENT 1TOAEP:NRC:1180A Page5DESCRIPTION OFPROPOSEDTECHNICAL SPECIFICATION CHANGESTheproposedchangesarelistedbelow.Theyareidentical forbothunits.1~PT/S3.4.6.2f.Replaceinitsentirety.
2.T/S3.4.6.2APPLICABILITY:
Delete"**"andreplacewitha"*"3.T/S3.4.6.2ACTIONc.Delete"exceptwhen...by50$ormore."T/S3.4.6.2ACTIONc,footnote*.Deletethefootnote.
5.T/S3.4'.2APPLICABILITY, footnote**.ChangetheIt'lltoII*II6.T/S4.4.6.2.2.
Replaceitwiththefollowing text:"Eachreactor'oolantsystempressure.isolation valvespecified inTable3..4-.0'shallbe.,'demonstrate@'
OPERABLE'pursuant
.to..'Sp'ecification 4:05."7.T/S3/4.6.2,Table3.4-0.ReplacetheTableinitsentirety.
10CFR502SIGNIFICANT HAZARDSCONSIDERATION ANALYSISPer10CFR50.92,aproposedamendment toanoperating licensewillnotinvolveasignificant hazardsconsideration iftheproposedamendment satisfies thefollowing threecriteria:
1)Doesnotinvolveasignificant increaseintheprobability orconsequences ofan.accidentpreviously
- analyzed, 2)doesnotcreatethepossibility ofanewordifferent kindofaccidentfromanaccidentpreviously analyzedorevaluated, or3)doesnotinvolveasignificant reduction inamarginofsafety.
ATTACHMENT 1TOAEP:NRC:1180A Page6Criterion 1TheISLOCAisnotoneoftheaccidents previously analyzedinChapter14,SafetyAnalysis, oftheCookNuclearPlantUpdatedFinalSafetyAnalysisReport.Chapter14analyzesthelargebreakLOCAinSection14.3.1,and"lossofreactorcoolantfromsmallrupturedpipesorfromcracksinlargepipeswhichactuatestheECCS,"orsmallbreakLOCAinSection14.3.2.Therefore, theproposedT/Ssmodifications totheReactorCoolantSystempressureisolation valvesinTable3.4-0,willnotincreasetheprobability ortheconsequences ofthelargebreakorthesmallbreakLOCAspreviously analyzedfortheCookNuclearPlant.Criterion 2TheReactorCoolantSystempressureisolation valvesinTable3.4-0oftheT/SswereaddedbecauseWASH-1400 identified theISLOCAasasignificant contributor tocoredamagefrequency.
Theproposedmodifications ofthesubjectvalvesTechnical Specification surveillance requirements torelyonthetestingrequirements mandatedbytheIn-Service TestingProgramofASMEXIdoesnotcreatethepossibility ofanewordifferent kindofaccidentfromthelargebreakorthesmallbreakLOCAspreviouely
.analyzed'or.
theCookNuclearPlant.,I~riterfon 3Theproposedmodifications totheReactorCoolantSystempressureisolation valvestestingrequirements inTable3.4-0oftheT/Ss,willresultinthesevalvesonlybeingtestedonarefueling outagefrequency aspartoftheASMEB6PVCodeSectionXIISTProgram.Thissomewhatreducedtestingfrequency willresultinaslightincreaseintheISLOCAinitiating eventfrequency, andISLOCAcontribution tocoredamagefrequency by5.4%,fromlower5.00E-08/reactor yeartomid5.00E-08/reactor year.Thisinsignificant increasewillnotaffecttheoverallcoredamagefrequency of6.26E-05/reactor year.Therefore, itisconcluded thattheproposedchangestotheT/Srequirements fortheReactorCoolantSystempressureisolation valvesinTable3.4-0,willnotresultinasignificant reduction inthemarginofsafetythatexistsatCookNuclearPlanttopreventanISLOCAortomitigatetheconsequences ofanISLOCA.
ATTACHMENT 1TOAEP:NRC:1180A Page7REFERENCES WASH-1400/NUREG 75/014,ReactorSafetyStudy:AnAssessment ofAccidentRisksinU.S.Commercial NuclearPlants,USNRC,October1975.2.USNRCLettertoallLWRLicensees:
LWRPrimaryCoolantSystemPressureIsolation Valves,February25,1980.3.AEP:NRC:0371, ReactorCoolantSystemPressureIsolation Valves,March24,1980.4.Letter,S.A.Varga,USNRCtoJ.Dolan,IndianaandMichiganElectricCompany,OrderforModification ofLicensesConcerning PrimaryCoolantSystemPressureIsolation Valves,April20,1981.5.USNRCGenericLetter(GL)87-06,"PeriodicVerification ofLeakTightIntegrity ofPressureIsolation Valves,"March13,1987.6.7..AEP:NRC:1041, GenericLetter87-06,PeriodicVerification
'of'LeakTight'Integrity of"Pressure Isolation Valves>..November 12,3.987,'X~USNRCInformation Notice92-36,."Intersystem LOCAOutsideContainment,"
May,7,1992.8.Initiation oftheIndividual PlantExamination forSevereAccidentVulnerabilities
-10CFR50.54(f),
GenericLetterNo.'8-20, November23,1988.9.AEP:NRC:1082E, Individual PlantExamination Submittal, ResponsetoGenericLetter88-20,May1,1992.10.AEP:NRC:1082F, Individual PlantExamination ResponsetoNRCQuestions,
.February 24,1993.AEP:NRC:1180, Technical Specification ChangeRequest,ReactorCoolantSystemPressureIsolation Valves,November15,1993.12.NUREG-1431, StandardTechnical Specifications forWestinghouse Plants,September 1992.
ATTACHMENT 2TOAEP:NRC:1180A MARKED-UP TECHNICAL SPECIFICATION PAGES
