ML17332A343

Application for Amends to Licenses DPR-58 & DPR-74,revising TS Re RCS Pressure Isolation Valves

ML17332A343
Person / Time
Site:	Cook
Issue date:	10/07/1994
From:	FITZPATRICK E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
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ML17332A344	List: ML17332A343 ML17332A345
References
AEP:NRC:1180A, NUDOCS 9410170196
Download: ML17332A343 (17)

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

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