ML17334B343

Application for Amend to License DPR-58,changing Tech Spec 3/4.7.1.5.1.b, Steam Generator Stop Valves, & 3.3-5 5.h, 6.h & 7.c.Amend Ensures Valve Closure within Eight Seconds on Closure Actuation Signal

ML17334B343
Person / Time
Site:	Cook
Issue date:	01/31/1990
From:	ALEXICH M P INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	MURLEY T E NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17328A555	List: ML17328A554 ML17334B343
References
AEP:NRC:1120, NUDOCS 9002070466
Download: ML17334B343 (14)

Text

ACCELERATED DUTIONDEMONATIONSYSlHMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9002070466 DOC.DATE:

90/01/31NOTARIZED:

NO'OCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,Indiana&05000315AUTH.NAMEAUTHORAFFILIATION ALEXICH,M.P.

IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.

DocumentControlBranch(Document ControlDesk)

SUBJECT:

Application foramendtoLicenseDPR-58,changing TechSpec3/4.7.1.5.

l.b,"SteamGenerator StopValves."DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:

GeneralDistribution NOTESRI.D'S/RECIPIENT IDCODE/NAME PD3-1LAGIITTER,J.

INTERNAL:

NRR/DET/ECMB 9HNRR/DST8E2NRR/DST/SICB 7ENUDOCS-ABSTRACT OGC/HDS1RES/DSIR/EIB EXTERNAL:

LPDRNSICCOPIESLTTRENCL11551111111110111111RECIPIENT IDCODE/NAME PD3-1PDNRR/DOEA/OTSB1 1NRR/DST/SELB 8DNRR/DST/SRXB 8EOCQ~QCBREGFILENRCPDRCOPIESLTTRENCL11111111'011'1DDS',I,NOTETOALL"RIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWAS'}CONTACTTHE,DOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEEDtTOTALNUMBEROFCOPIESREQUIRED:

LTTR21,ENCL19D

~~I indianaMichiganPowerCompanyP.O.Box16631Columbus, OH432168AEP:NRC:1120 DonaldC.CookNuclearPlantUnit1DocketNo.50-315LicenseNo.DPR-58EXPEDITED TECHNICAL SPECIFICATION CHANGEREQUESTSTEAMGENERATOR STOPVALVESU.STNuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyJanuary31,1990

DearDr.Murley:

Thisletteranditsattachments constitute anapplication foranexpedited technical specification (T/S)changeforDonaldC.CookNuclearPlantUnit1,Specifically, weproposetochangeT/S3/4,7.1.5.1.b, "SteamGenerator StopValves,"suchthatfullvalveclosureiswithin8secondsonany-closureactuation signal.Thereasonsforthechangeandourevaluation concerning significant hazardsconsideration areprovidedinAttachment 1.TheproposedrevisedT/SpagesareincludedinAttachment 2.Attachment 3andAttachment 4containtheanalysisofmainsteamlinebreakinsidecontainment andofsteamlinebreakcoreresponse, whichwerenotpreviously providedtotheNRC.(Thesteamlinebreakinsidecontainment attachment willalsobesubmitted withtheUnit2fuelreloadsubmittal.)

ThisletteralsoproposeschangestoT/STable3.3-55.h,6.h,and7.c.Thesearethesteamlineisolation responsetimesrequiredfortheaccidentanalyses.

Webelievethattheproposedchangewillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.

ThechangehasbeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheNuclearSafetyDesignReviewCommittee atitsnextregularly scheduled meeting.Incompliance withtherequirements of10CFR50.91(b)(1),

copiesofthisletteranditsattachments havebeentransmitted toMr.R.C.CallenoftheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.>002070%66 900lslPDRADGCK05000315PDC.

Dr.T.E.Murley-2-AEP:NRC:1120 Thisdocumenthasbeenpreparedfollowing Corporate procedures thatincorporate areasonable setofcontrolstoensureitsaccuracyandcompleteness priortosignature oftheundersigned.

Sincerely, M.P.AlexichVicePresident ldpAttachments cc:D.H.Williams, Jr.A.A.Blind-BridgmanR.C.CallenG.CharnoffNFEMSectionChiefA.B,Davis-RegionIIINRCResidentInspector

-Bridgman ATTACHMENT 1TOAEP:NRC:1120 REASONSAND10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNIT1TECHNICAL SPECIFICATIONS 9002070466 Attachment 1toAEP:NRC:1120 Page1Introduction Theprimarypurposeofthesteamgenerator stopvalves(mainsteamisolation valve[MSIVs])istopreventexcessive blowdownofthesteamgenerators.

Therearefourtechnical specifications (T/Ss)forDonaldC.CookNuclearPlantUnit1associated withtheclosuretimeoftheMSIVs.T/S4.7.1.5.b requiresthateachMSIVbedemonstrated operablebyverifying fullclosurewithinfivesecondsonanyclosureactuation signalwhileinhotstandbywithTavggreaterthanorequalto541Fduringeachreactorshutdownexcept0thatverification offullclosurewithinfivesecondsneednotbedetermined moreoftenthanonceper92days.ThethieeotherT/Ssarethesteamlineisolation responsetimerequirements listedinT/S3.3'.1Table3.3-5"Engineered SafetyFeaturesResponseTimes."Thesearelistedbelow.Item5.hSteamlineisolation resulting fromsteamflowintwosteamlines-highcoincident withTavg--low-low(lessthanorequalto10.0seconds)Item6.hSteamlineisolation resulting fromsteamflowintwosteamlines-highcoincident withsteamlinepressure-low(lessthanorequalto8.0seconds)Item7.cSteamlineisolation resulting fromcontainment pressure--high-high (lessthanorequalto7.0seconds)Evaluation TheCookNuclearPlantsafetyanalysesthatassumeactuation oftheMSIVsandsteamlineisolation includethefollowing events:,steamlinebreakcoreresponse, steamlinebreakmass/energy releasesforinsidecontainment integrity

analysis, steamlinebreakmass/energy releasesforoutsidecontainment equipment qualification

analysis, steamgenerator tuberupture(SGTR),andlossofcoolantaccident(LOCA).TheLOCAanalysesdonotassumeactuation timesfortheMSIVs,butconservatively assumesteamlineisolation occursatreactortrip.Theothersafetyanalyseslistedaboveassumeanoverallengineered safetyfeatures(ESF)responsetimeforsteamlineisolation fromthetimethattheisolation setpointisreached

Attachment 1toAEP:NRC:1120 Page2SteamLineBreakCoreResonseTheUnit1licensing basisanalysisperformed forthereducedtemperature andpressureprogramassumedanESFresponsetimewhichincludesanadditional threesecondsforsteamlineisolation withrespecttotheT/Srequirements.

Thus,athree-second increaseintheT/SMSIVclosuretimeandsteamlineisolation ESFresponsetimesissupported bytheanalysis.

Thisanalysiswassubmitted inAEP:NRC:1067 andapprovedbytheNRCbySERdatedJune9,1989.AlthoughtheWCAP-11902 analysisspecified thataMSIVclosuretimeofsevensecondswasassumed,Westinghouse hasdocumented thataneight-second MSIVclosuretimeissupported.

Theeight-second MSIVclosuretimerepresents anincreaseofthreesecondsfromthecurrentT/Slimitoffiveseconds.Assuch,theWCAP-11902 steamlinebreakcoreresponseanalysissupportsarelaxation oftheMSIVclosuretimerequirement.

Thisdocumentation iscontained asAttachment 4ofthisletter.SteamLineBreakMEReleasesInsideContainment Ananalysishasrecentlybeenperformed tosupporttheproposedtransition toWestinghouse 17x17V-5fuelforUnit2whichincludesanadditional threesecondsforsteamlineisolation withrespecttotheT/Srequirements (WCAP-11902, Supplement 1,contained asAttachment 3tothisletter).Thisanalysisbounds'both Units1and2andisapplicable forbothV-5andANFfueltypes,including afullcoreofANFfuel,aslongastheT/Slimitsoncoreparameter assumptions (e.g.,moderator coefficient) aremet.Thus,themass/energy releaseinputtothecontainment responseanalysisremainsvalidandathree-second increaseintheT/SMSIVclosureandsteamlineisolation ESFresponsetimesissupported bytheanalysis.

SteamLineBreakMEReleasesOutsideContainment Thecurrentlicensing basismass/energy releasedataforuseinoutsidecontainment equipment qualification fortheCookNuclearPlantUnits1and2areprovidedinWCAP-10961.

Units1and2arecoveredbytheWCAPCategory3andCategory1analysesrespectively.

Themass/energy releasecalculations assumedanESFresponsetimeforsteamlineisolation consistent withtheT/Srequirements.

Ourcurrentequipment qualification analysiswassuppliedbyImpell,(AEP:NRC:0775AJ).

Theeffectofincreasing thesteamlineisolation timeistoslightlyincreasethesteamflowatanygiventimefollowing isolation whileslightlydelayingtheonsetofsuperheated steamreleases.

AllcasesanalyzedintheWCAPwouldbeexpectedtobesimilarly affectedbythissmalladditional delay.TheWCAPCategory1cases1,16and59,alllargebreakcases(4.6ft),were Attachment 1toAEP:NRC:1120 Page3identified aslimitingbyImpellandusedtoboundbothUnits1and2.Theselimitingcaseswerereanalyzed byWestinghouse assuminganoverallsteamlineisolation timewhichincludesanadditional threesecondswithrespecttotheT/Srequirements.

AEPSCevaluated theeffectsofthismassandenergyreleaseratechangeonthesteamenclosure temperatures andconcluded thattheinstruments remainedinsidetheiranalyzedlimits.TheeffectoflongerMSIVclosuretimesimplyshiftsthetemperature peakslightlyoutwardintime,butdoesnotincreaseitsseverity.

Therefore, theincreaseinMSIVclosuretimewouldnotaffectthechoiceofwhichsteamlinebreaksizewaslimiting.

SteamGenerator TubeRutureTheSGTRaccidentanalysisforCookNuclearPlantUnits1and2wasreviewedtodetermine theimpactofanincreaseintheMSIVclosureandsteamlineisolation timesbythreeseconds.IntheSGTRanalysis, theprimary-to-secondary breakflowwasassumedtobeterminated at30minutesafteraccidentinitiation, buttheoperatoractionstoterminate thebreakflowwerenotexplicitly modeledintheanalysis.

Theoperatoractionsincludeisolation oftherupturedsteamgenerator, whichrequirestheclosureoftherupturedsteamgenerator MSIV.SinceMSIVclosureisnotexplicitly modeledintheanalysisandanadditional threesecondstoclosetherupturedsteamgenerator MSIVisrelatively shortcomparedtotheassumedtotalrecoverytimeof1800seconds,itisconcluded thattheincreased timeforMSIVclosureandsteamlineisolation willnotaffecttheconclusions oftheFSARSGTRanalysisnortheconclusions oftherecentanalysescompleted forupratedpowerplusrevisedtemperature andpressureoperation.

Areviewwasperformed byAEPSCoftheoff-siteradiological doseconsequences ofaddingthreesecondstothesteamgenerator stopvalveclosuretime.Theadditional threesecondswouldresultinanin]ection of210poundsofadditional reactorcoolanttoaninitialtotalmassofreactorcoolantof125,000poundsassumedintheFSARforaSGTR.Thiscorresponds toafractional increaseof0.00168forthetotalreactorcoolantmasstransferred tothesteamgenerator.

Withtheoff-sitedosesbeingproportional totheamountofactivityreleased, andassumingthatallofthereactorcoolanttransferred totherupturedsteamgenerator isreleased, theoff-sitedoseswouldalsoincreaseby0.00168.Thisminutefractional increaseintheoff-sitedosescannotbedifferentiated fromthegraphsofthedoseconsequences foraSGTRaccident.

Basedonthisreview,ithasbeenconcluded thattheadditional threesecondsdonotimpacttheFSARenvironmental consequences

ofaSGTR, Attachment 1toAEP:NRC:1120 Page4SmallandLareBreakLOCAThesmallbreakandlargebreakloss-of-coolant:

(SBLOCAandLBLOCArespectively) analysesarenotadversely affectedbyincreased MSIVclosureandsteamlineisolation times.TheSBLOCAandLBLOCAanalysesassumethatsteamgenerator isolation occursimmediately afterthereactortriplowpressurizer pressuresetpointisreached.Byisolating thesteamgenerators atthetimeofreactortrip,thestoredenergyinthesecondary isconservatively greaterthanwhatwouldexistiftheanalysesmodelledalatersteamgenerator isolation.

FortheSBLOCAanalysis, thehigherenergyinthesecondary isconservative sincetheprimary-to-secondary heattransferrateisreduced.IntheLBLOCAanalysis, theearliersteamgenerator isolation timeincreases thesecondary-to-primary heattransfer, whichisconservative.

Therefore, anincreaseinMSIVclosureandsteamlineisolation timesbythreesecondsdoesnothaveanimpactonSBLOCAandLBLOCAanalyses.

LOCABlowdownForcesHotLeSwitchover toPrecludeBoronPreciitationPost-LOCA Lon-TermCoreCoolinSubcriticalit andPose-LOCA Lon-TermCoreCoolinMinimumFlowReactorvesselandloopLOCAblowdownforces,hotlegswitchover toprecludeboronprecipitation, post-LOCA long-term corecoolingsubcriticality, andpost-LOCA long-term corecoolingminimumflowarenotadversely affectedbytheproposedchange.Increasing MSIVclosureandsteamlineisolation timesdoesnotadversely affectthenormalplantoperating parameters, thesafeguards systemsactuations oraccidentmitigation capabilities important toaLOCA;ortheassumptions usedintheLOCA-related analyses.

Inaddition, theproposedchangedoesnotcreateconditions morelimitingthanthoseassumedintheLOCAanalyses.

Justification forReuestandSinificantHazardsConsideration Webelievethatincreasing theMSIVclosuretimebythreesecondswillnotadversely impactpublichealthandsafety.Anincreased steamlineisolation responsetimehasbeenevaluated withrespecttotheCookNuclearPlantUnit1safetyanalyses.

Baseduponpreviously performed

analyses, thesteamlinebreakcoreresponse, steamlinebreakmass/energy releasesforinsidecontainment integrity

analysis, SGTR,andLOCAanalysessupportanincreaseintheMSIVclosuretimeisolation timesofthreesecondswithrespecttotheT/Srequirements, Forsteamlinebreakmass/energy releasesoutsidecontainment, limitingcaseshavebeenreanalyzed assumingasteamlineisolation timethreesecondslongerthanthecurrentT/Srequirements.

Also,revisedmass/energy datawereevaluated byAEPSC,resulting intheconclusion thattheincreaseinMSIVclosuretimewouldnotaffectthechoiceofwhichsteamlinebreaksizewaslimiting,

'f Attachment 1toAEP:NRC:1120 Page510CFR50.92CriteriaPer10CFR50.92,aproposedamendment willnotinvolveasignificant hazardsconsideration iftheproposedamendment doesnot:1)involve,asignificant increaseintheprobability orconsequences ofanaccidentpreviously

analyzed, 2)createthepossibility ofanewordifferent kindofaccidentfromanaccidentpreviously analyzedorevaluated, or3)involveasignificant reduction inamarginofsafety.Ourevaluation oftheproposedchangewithrespecttothesecriteriaisprovidedbelow.Criterion 1Basedonthesafetyanalysesperformed byWestinghouse forthesteamlinebreakcoreresponse, steamlinebreakmass/energy releasesforinsidecontainment integrity, SGTR,andLOCA,webelievethattheproposedT/Schangetoincreasethesteamlinebreakisolation responsetimeandthesteamgenerator stopvalveclosuretimebythreesecondswillnotinvolveasignificant increaseintheprobability orconsequences ofapreviously analyzedaccident.

Criterion 2Thethree-second increaseforthesteamlineisolation responsetimewillnotchangethedesignoroperation oftheplant.Therefore webelievethatthischangewillnotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously analyzedorevaluated.

Criterion 3Basedonthesafetyanalysesperformed byWestinghouse forthesteamlinebreakcoreresponse, steamlinebreakmass/energy releasesforinsidecontainment integrity, SGTR,andLOCA,webelievethattheproposedT/Schangeincreasing thesteamlinebreakisolation responsetimeandthesteamgenerator stopvalveclosuretimebythreesecondswillnotinvolveasignificant reduction inamarginofsafety.

Attachment 1toAEP:NRC:1120 Page6Lastly,wenotethattheCommission hasprovidedguidanceconcerning thedetermination ofsignificant hazardsbyproviding certainexamples(48FR14870)ofamendments considered notlikelytoinvolvesignificant hazardsconsideration.

Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobability ofoccurrence orconsequences ofapreviously analyzedaccident, buttheresultsofwhicharewithinlimitsestablished asacceptable.

Forthereasonsdetailedabove,webelievethischangefallswithinthescopeofthisexample.Therefore, webelievethischangedoesnotinvolvesignificant hazardsconsideration asdefinedin10CFR50.92.