ML17325B522

LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing

ML17325B522
Person / Time
Site:	Cook
Issue date:	03/29/1999
From:	BERRY L R INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17325B521	List: ML17325B519 ML17325B522
References
LER-99-001, LER-99-1, NUDOCS 9904090204
Download: ML17325B522 (1)

Text

NRCForn366U.S.NUCLEARREGULATORY COMMiSSION (6-1998)LICENSEEEYENTREPORT(LER)(Seereverseforrequirednumberofdigits/characters foreachblock)APPROVEOBYOMBNo.31600104EXP(RES06130I2001 fSTSIIATED BURDENPERRESPONSETOCOMPLYWITHT)SSMANDATORY WfORMATION COLLECTION REOUESTI500HRS.REPORTEDLESSONSLEARNEDAREWCORPORATED WTOTHELICENSING PROCESSJJIOFEOBACKTOeeUSTRY.fORWARDCOMMENTSREGA)CING BURDENESTIMATETOTHESP'ORMATION ANORECORDSMANAGEMENT BRANCHITSF55).U.S.NUCLEARREGIAATORY COMMISSION.

WAS)eNGTON.

DC205554ool.

AtTOTHEPAPERWORK RECUCTION PROJECT(M500101),

CFFCEOfMANAGEMENT ANDBUDGET.WASHINGTON.

DC205OSFACILITYNAME(1)TITLE(4)CookNuclearPlantUnit2DOCKETNUMBER(2)05000-316 PAGE(3)1of1DegradedComponent CoolingWaterFlowtoContainment MainSteamLinePenetrations EVENTDATE(5)LERNUMBER(6)REPORTDATE(7)OTHERFACILITIES INVOLVED(8)MONTH06DAY10YEARYEARSEQUENTIAL NUMBER1996,1999-001'EVISIONNUMBER00MONTHDAYYEAR03291999AILINAMCookPlantUnit1AILIYHAM05000-315 KNUMOPERATING MODE(9)POWERLEVEL(10)10020.2201(b)20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20,2203(a)(2)(v}

20.2203(a)(3)(i) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1

}50.36(c)(2)

LICENSEECONTACTFORTHISLER(12)50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a}(2)(viii) 50.73(a)(2)(x) 73.71OTHERSpeorryinAberrso(belowornNRCForm366ATELEPHONE NUMBER(Inc@deAreeCode)THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFR():(Checkoneormore)(11)LyleR.Berry,Regulatory Compliance Engineer(616)465-5901x2637COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT(13)CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TOEPIXPP,,d.SCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TOEPIXSUPPLEMENTAL REPORTEXPECTED(14)XYES(IfYes,completeEXPECTEDSUBMISSION DATE)NOEXPECTEDSUBMISSION DATE(15MONTHDAY06251999Abstract(Limitto1400spaces,i.e.,approximately 15single-spaced typewritten lines)(18)OnFebruary26,1999,duringanengineering reviewoftheUnit2Component CoolingWaterSystem(CCW),itwasidentified thatpoweroperation waspermitted inJune1996withdegradedCCWflowtothecoolersforcontainment penetrations 2-CPN-3and2-CPN-4.Themainsteamheadersforsteamgenerators 22and23passthroughthesepenetrations.

Operating withthedegradedCCWtothesecoolersmayhaveresultedinexcessive thermalstressonthepenetration sleeves/liners.

TheUpdatedFinalSafetyAnalysisReport(UFSAR)creditsthepenetration coolersformaintaining thetemperature ofadjacentconcretelessthan150degreesF.Atthetimeoftheevent,containment exteriorsurfaceconcretetemperatures weremeasuredatamaximumof155degreesF.Operability determinations performed atthetimeoftheevent,tojustifycontinued operation withdegradedCCWflowtothemainsteamlinepenetrations, havebeenre-evaluated andfoundtobe,inadequate.

Thiseventwasreportedviaa4'hournon-emergency Emergency Notification System(ENS)reportonFebruary27,1999,pursuanttotherequirements of10CFR50.72(b)(2)(i).

ThisLERisbeingsubmitted pursuanttotherequirements of10CFR50.73(a)(2)(ii)(B) asaneventorcondition thatresultedinthenuclearpowerplantbeinginacondition thatwasoutsidethedesignbasisoftheplant.Initialinvestigations indicatethatthecauseforthiseventwasaninadequate understanding ofthedesignbasisforthecontainment penetration coolers.Additional investigations toassesspotential degradation totheconcrete, linersandsleevesatthesepenetrations areongoing.Theresultsofthoseinvestigations, including identified rootcause(s),

preventive actionsandsafetysignificance willbeprovidedwhencompleted.

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