ML17325B603

Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment.

ML17325B603
Person / Time
Site:	Cook
Issue date:	05/21/1999
From:	RENCHECK M W INDIANA MICHIGAN POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:C0599-0, AEP:NRC:C599, GL-98-04, GL-98-4, NUDOCS 9905280222
Download: ML17325B603 (15)

Text

CATEGORY' REGULA'iYINFORMATION DISTRIBUTI

.SYSTEM(RIDS)ACCESSION NBR:9905280222 DOC.DATE:

99/05/21NOTARIZED:

YESDOCKETFACIL:50315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NMT8AUTHORAFFILIATION RENCHECK,M.W.

IndianaMichiganPowerCo.-(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION RecordsManagement Branch(Document ControlDesk)

SUBJECT:

ProvidesresponsetoNRCGL98-04,"Potential forDegradation ofECCS&Containment SpraySysAfterLOCABecauseofConst&Protective CoatingDeficiencies

&ForeignMatlinContainment."

TDISTRIBUT1'ON CODE:AOSODCOPIESRECEIVED:LTR IENCLISIZE:ITITLE:GenericLetter98-04-Potential fortheDegradation oftheEmergency ENOTES:RECIPIENT IDCODE/NAME STANG,JCOPIESLTTRENCL11RECIPIENT IDCODE/NAME COPIESLTTRENCLINTERNAL:

FILECENTER01~11~NRR/DLPM/LPD3 11NRR/DE/EMCB NRR/DSSA/SPLB 1111EXTERNAL:

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i,'i)NOTETOALL"RIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083ITOTALNUMBEROFCOPIESREQUIRED:

LTTR6ENCL"6 IndianaMichigan~.PowerCompany~500CircleDriveBuchanan, Ml491071395

ÃINDIANANICHIGAlltI POWMMay21,1999AEP:NRC:C0599"01 DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskHailStop0-P1-17Washington, D.C.20555-0001 DonaldC.CookNuclearPlantUnits1and2GENERICLETTER98-04:POTENTIAL FORDEGRADATION OFTHEEMERGENCY CORECOOLINGSYSTEMANDTHECONTAINMENT SPRAYSYSTEMAFTERALOSS-OF-COOLANT ACCIDENTBECAUSEOFCONSTRUCTION ANDPROTECTIVE COATINGDEFICIENCIES ANDFOREIGNMATERIALINCONTAINMENT

Reference:

LetterAEP:NRC:1260GH,"DonaldC.CookNuclearPowerPlant,Units1and2,ENFORCEMENT ACTIONS98-150,98-151,98-152AND98-186,REPLYTONOTICEOFVIOLATION DATEDOCTOBER13,1998,"datedMarch19,1999.Gentlemen:

Inaccordance with10CFR50.54(f),

IndianaMichiganPowerCompany(I&H)herebyprovidestheresponsetoNRCGenericLetter98-04.Thisgenericletterrequireslicensees toprovideinformation regarding theirprogramsforthecontrolofprotective coatingsinsideofthecontainment structure.

Therequested information includesprocurement ofcoatings, qualification testingofcoatings, surfacepreparation andapplication of'oatings, andsurveillance andmaintenance activities associated withcoatings.

Additionally, thegenericletterrequestsinformation aboutunqualified coatingsthatmaybelocatedinside'he:containment structure.

Theattachment tothisletterprovidestherequiredresponsetoitems(1)and(2)ofthegenericletter.Thislettercontainsonecommitment, whichistoenhanceplantprocedures thatcontrolcoatingsinsidecontainment.

Currentplansaretohavetheseplantprocedures developed byOctober30,1999.',,','0Inadditiontoresponding tothisgenericletter,I&Hiscurrently reviewing recirculation sumpoperability issues,including sumpblockagecausedbyaccidentgenerated debris.Asnotedinthereferenced letter,debrisgeneration andtransport 9905280222 O'F0521PDRADQCK05000315PPDR AEP:NRC:C0599-01 U.S.NuclearRegulatory Commission Page2evaluations havebeenperformed, unwantedmaterialhasbeenremovedfromthecontainment, andprocedures andspecifications havebeenwrittenorrevisedtobettercontrolfibrousmaterials insideofcontainment.

I&MplanstocontinuetheseeffortsaspartoftheCookNuclearPlantrestarteffort.Therequireddateforsubmittal oftherequested information was.November12,1998.TheCookNuclearPlantiscu'rrently shutdownandinanextendedoutage.I&M'sdelayinproviding thisresponseisduetothededication ofengineering andtechnical supportresources totheCookNuclearPlant'srestarteffort.TheNRCProjectManagerfortheCookNuclearPlantwasinformedofthisdelay.Sincerely, J@r/M.W.RencheckVicePresident NuclearEngineering SWORNTOANDSUBSCRIBED BEFOREMETHIScd/DAYOFQQ.1999JNICENLSiCKERSt8htyPub."c,BerrisnCornty,MMyCommission ExpirosFeb.16,2001NOTARYPUBLICMyCommission Expires:/4~dYAttachment

/rgvA.C.BakkenJ.E.Dyer,w/attachment MDEQ-DW&RPDNRCResidentInspector, w/attachment R.Whale

/,i>>rI' U.S.NuclearRegulatory Commission Page3Ibc:T.P.Beilmanwattachmen AEP:NRC:C0599-01

/tJ.J.EutoFOLXO,w/attachment B.J.HickleG.HonmaD.F.Kunsemiller/J.

Burford/M.

J.GumnsM.W.Rencheck/S.

A.Greenlee/D.

J.Garner/D.H.So/B.C.Mickatavage J.F:Stang,Jr.,-NRCWashington, DC,w/attachment Attachment toAEP:NRC:C0599-01 RESPONSETOGENERICLETTER98-04 Attachment toAEP:NRC:C0599-Ol Page1ResonsetoGenericLetter(GL)98-04Dated,Jul 14,1998OnJuly14,1998,theNuclearRegulatory Commission (NRC)issuedGL98-04regarding theimpactofpotential coatingdebrisontheoperation ofsafetyrelatedsystems,structures, andcomponents (SSC)duringapostulated designbasislossofcoolantaccident(LOCA).Protective coatingsarenecessary insidecontainment tocontrolradioactive contamination andtoprotectsurfacesfromerosionandcorrosion.

However,detachment ofthecoatingsfromthesubstrate mayresultintheemergency corecoolingsystem(ECCS)beingunabletosatisfytherequirements of10CFR50.46(b)(5),

i.e.,toprovidelong-term cooling,and-mayresultinthesafetyrelatedcontainment spraysystem(CTS)"beingunabletocontrolcontainment pressureandradioactivity releasesfollowing aLOCA.TheGLrequestsinformation under10CFR50.54(f)toevaluateaddressees'rograms forensuringthatServiceLevel1protective coatings(coatings whosefailurecouldadversely affecttheoperation ofpost-accident fluidsystems)insidecontainment donotdetachfromtheirsubstrate duringadesignbasisLOCAandinterfere withtheoperation oftheECCSandCTS.Thespecificrequestsareaddressed below.GenericLetterItem1reuiredthefollowin(1)Provideasummarydescription oftheplant-specific programorprogramsimplemented toensurethatServiceLevel1'protective coatingsusedinsidethecontainment areprocured, applied,andmaintained incompliance withapplicable regulatory requirements andtheplant-specific licensing basisforthefacility.

Includeadiscussion ofhowtheplant-specific programmeetstheapplicable criteriaof10CFRPart50,AppendixB,aswellasinformation regarding anyapplicable standards, plant-specific procedures, orotherguidanceusedfor:(a)controlling theprocurement ofcoatingsandpaintsusedatthefacility; (b)thequalification testingofprotective coatings; and(c)surfacepreparation, application, surveillance, andmaintenance activities forprotective coatings.

Maintenance activities involvereworking degradedcoatings, removingdegradedcoatingstosoundcoatings, correctly preparing thesurfaces, applyingnewcoatings, andverifying thequalityofexistingcoatings.

ResponsetoItem1TheCookNuclearPlantcontrolstoensurethatServiceLevel1protective coatingsusedinsidecontainment meetregulatory requirements includetheelementsdiscussed below.Allareadministered undertheCookNuclearPlant'squalityassurance program.

Attachment toAEP:NRC:C0599-01 Page2ISpecificResponseto(1)(a)Procurement ofServiceLevel1coatingsusedfornewapplications orrepair/replacement activities areprocuredfromavendorwithaqualityassurance programmeetingtheapplicable requirements of10CFRPart50appendixB.Theapplicable technical andqualityrequirements thatthevendorisrequiredtomeetarespecified intheprocurement documents (e.g.,specifications preparedinaccordance withanapprovedprocedure, andpurchaseorders).Acceptance activities byI&Mpersonnel areconducted inaccordance withprocedures thatareconsistent withANSIN45.2,"QualityAssurance

,ProgramRequirements forNuclearPowerPlants,"requirements (e.g.,receiptinspection, sourcesurveillance, etc.).Thespecification oftherequiredtechnical andqualityrequirements, combinedwiththeacceptance activities, providesadequateassurance thatthecoatingsreviewedmeettherequirements oftheprocurement documents.

Thefollowing specification isusedfortheprocurement ofServiceLevel1coatings.

DCC-CEST-134-QCN, "Procurement, Receipt,StorageandDocumentation ofProtective Coatings,"

Revision,7.

CoatingsonVendorSuppliedEquipment:

CookNuclearPlantunits1and2haveamixofvendor-supplied equipment insidecontainment thatwasprocuredwith"acceptable" aswellas"indeterminate" and"unacceptable" coatings(asdefinedinreference 1).Currently, therearenoprocedures inplacetotrack(e.g.,viaacoatingslog)theamountofindeterminate orunacceptable coatingsinsidecontainment.

Plantprocedures arebeingdeveloped tocontrolthequantityofindeterminate andunacceptable coatingsinsidecontainment.

Currentplansaretohavetheseplantprocedures developed byOctober30,1999.SpecificResponsetoitem(1)(b)Qualification testingofcoatingsisperformed bythecoatingsvendor.Therequirements forqualification testingofServiceLevel1coatingsusedfornewapplications orrepair/replacement activities insidecontainment arecontained inspecifications andmeetthefollowing regulatory guideandindustrystandards.

Regulatory Guide1.54,"QualityAssurance Requirements forProtective CoatingsAppliedtoWater-Cooled NuclearPowerPlants,"June1973.ANSIN101.4,1972"QualityAssurance forProtective CoatingsAppliedtoNuclearFacilities."

Attachment toAEP:NRC:C0599-01 Page3ANSIN101.2,1972"Protective Coatings(Paints)forLightWaterNuclearReactorContainment Facilities,"

applicable toicecondenser only.SpecificResponsetoitem(1)(c)Thesurfacepreparation, application, andinspection ofServiceLevel1coatingsusedinsidecontainment areperformed inaccordance withplantspecifications andprocedures andareintendedtomeettheapplicable portionsofCookNuclearPlant'slicensing basis.Documentation ofcompletion oftheseactivities isperformed pertherequirements oftheimplementing procedures.

Ageneralvisualexamination ofServiceLevel1coatingsinsidecontainment isperformed duringeachrefueling oranextendedoutageaspartof.theprotective coatingsinspection procedure.

Whenlocalized areasofdegradedcoatingsareidentified, theyareevaluated andscheduled forrepairinaccordance withtheprotective coatingsinspection procedure listedbelow.Thefollowing specifications andprocedures areusedtocontroltheapplication ofcoatings.

Specifications DCC-CEST-145-QCN, "PainterTraining, Qualification andCertification,"

Revision4.ES-CIVIL-0408-QCN, "Protective CoatingSystem:Requirements forMaterialSelection, SurfacePreparation, Application andInspection,"

Revision0.Procedures 800000-LTG-7400-01, "Qualification andCertification ofInspection, Test,Examination, AuditandNDEPersonnel,"

Revision0.Thisprocedure providestheeducational, experience,

physical, andcertification requirements forinspectors.

(227200-STG-5400-08, Revision0."Protective CoatingInspection,"

Thisprocedure specifies thatin-placeinspection ofcoatingsbeperformed duringeachrefueling outageandthattheinspection maybeperformed duringothermajoroutages.Theprocedure requiresthatanassessment ofthecoating's condition beperformed, acondition reportbewrittenforsignificant defectsanddeviations, andthataninspection reportbeprepared.

Attachment toAEP:NRC:C0599-01 Page412CHP5021;CCD.011, "Application ofProtective CoatingstoSteelSurfacesinAreasClassified asCoatingServiceLevel1andforCoatingServiceLevelIIILiningApplications,"

Revision3.Thisprocedure providesinstructions forsurfacepreparation, primecoatingapplication, finishcoatingapplication.

Italsoprovidesacceptance criteriaandaprovision formanagement review.12CHP5021.CCD.012, "Application ofProtective CoatingstoConcreteFloor,Wall,CeilingandBlockWallSurfacesinAreasClassified asCoatingServiceLevel1,"Revision2.Thisprocedure providesinstructions forsurfacepreparation ofconcretefloors,concretewalls,-ceilingsandblockwalls.Theprocedure providesinstructions forsurfacerapplication, primecoatingapplication, andfinishcoatingapplication.

Acceptance criteriaandaprovision formanagement reviewarealsoprovided.

GenericLetterItem2reuiresthefollowin(2)Information demonstrating compliance witheitheritem(i)or(ii):Forplantswithlicensing-basis requirements fortrackingtheamountofunqualified coatingsinsidethecontainment andforassessing theimpactofpotential coatingdebrisontheoperation ofsafety-relatedSSCsduringapostulated DBLOCA,thefollowing information shallbeprovidedtodemonstrate compliance:

(a)Thedateandfindingsofthelastassessment ofcoatings, andtheplanneddateofthenextassessment ofcoatings.

(b)Thelimitfortheamountofunqualified protective coatingsallowedinthecontainment andhowthislimitisdetermined.

Discussanyconservatism inthemethodusedtodetermine thislimit.(c)Ifacommercial-grade dedication programisbeingusedatyourfacilityfordedicating commercial-grade coatingsforServiceLevel1applications insidethecontainment, discusshowtheprogramadequately qualifies suchacoatingforServiceLevel1service.Identifywhichstandards orotherguidancearecurrently beingusedtodedicatecontainment coatingsatyourfacility, or, Attachment toAEP:NRC:C0599-01 Page5(ii)Forplantswithouttheabovelicensing-basis requirements, information shallbeprovidedtodemonstrate compliance withtherequirements of10CFR50.46(b)(5),

"Long-term cooling"andthefunctional capability ofthesafetyrelatedCTSassetforthinyourlicensing basis.Ifalicenseecandemonstrate thiscompliance withoutquantifying theamountofunqualified

coatings, thisisacceptable.

(a)Ifcommercial gradecoatingsarebeingusedatyourfacilityforServiceLevel1applications, andsuchQualitycoatingsarenotdedicated orcontrolled underyourAppendixBQualityAssurance Program,providetheregulatory andsafetybasisfornotcontrolling thesecoatingsinaccordance withsuchaprogram.Additionally, explainwhythefacility's licensing basisdoesnotrequiresuchaprogram.ResonsetoItem2TheCookNuclearPlantdoesnothavealicensing basisrequirement fortrackingtheamountofunqualified coatingsinsidecontainment.

Therefore, I&Misproviding thefollowing responsetoItem2(ii).Thefollowing description andreferenced materialdescribethelicensing basisfortheplantrelativetoconformance with10CFR50.46(b)(5),

"LongTermCooling."

Specifically, itaddresses theoperation oftheECCS,thefunctionofthesump,andtheregulatory basisforassumingamaximumsumpblockageof50%.TheCookNuclearPlantiscurrently evaluating theadequacyofthesumpinventory fortheECCSandCTSsystemsaspartoftherestartefforts.Thiseffort,althoughrelatedtothegenericletterconcerns, doesnotimpactthisresponse.

Thus,thissubmittal doesnotaddresseithertheECCSorCTSsystemissuesandresolutions.

AnyactionsrequiredasaresultoftheECCS/CTSevaluations willbeaddressed asapartoftherestarteffort.Theoperation oftheECCSfollowing aLOCAisdividedinto2phases:1)theinjection phaseinwhichanyreactivity" increaseattending theaccidentisterminated, initialcoolingofthecoreisaccomplished, andthecoolantlostfromtheprimarysystemisreplenished; and2)therecirculation phaseinwhichlongtermcorecoolingisprovidedduringtheaccidentrecoveryperiod.Thepotential impactofthedegradation ofprotective coatingsusedinsidecontainment wouldoccuronlyduringtherecirculation Attachment toAEP:NRC:C0599-01 Page6EphasewhenthewaterrequiredbytheECCSandtheCTSisobtainedfromtherecirculation sump.Thesumpdesignprovidessufficient flowareaoverthetrashcurbaheadofthesumpandadequatenetpositivesuctionheadfortheresidualheatxemoval(RHR)andCTSpumpstooperateintherecirculation mode.Waterflowingintothesumppassesthroughthecoarseandfinescreensanddownwards underthecranewall.Theflowisthenturnedupwardsandentersthetwinrecirculation pipesconnecting thesumptotheRHRandCTS.Theadjacentcontainment sumpisalsoequippedwithcoarseandfinescreensatitsentrance.

Thecontainment andtherecirculation sumpsareconnected viaan8-inchpipenearthebottomofthesumps.Therecirculation sumpisprotected attheentrybycoarseandfinescreenssupported withinasubstantial frame.Thecoarsescreen(grating) isinstalled infrontofthesumptopreventlargematerials frompassingandthefine(1/4-inch mesh)screenisintendedtostopmaterialcapableofpluggingthe3/8-inchcontainment spraynozzles.Additionally, thecontainment sumpentranceisalsoprotected withacoarsescreenand1/4inchwiremeshinasimilarmanner.Fortherecirculation sump,thescreensactasflowstraighteners andmitigatevortexformation byequalizing localvelocitydifferences.

Additionally, thesumpisdesignedwitharelatively largeflowarea,allowinglowwatervelocities, suchthatbuild-upofdebrisagainstthescreensisminimized.

Thelowvelocities makeitunlikelythatairbubblesenterintothepumpsuctionareaofthesump.AsnotedintheNRCsSafetyEevaluation Report(SER)datedJuly2,1982thecontainment recirculation sumpdesignmeetstheintentoftheapplicable sectionsofRegulatory Guides1.68,1.79,and1.82,Revision0.Inconformance withRegulatory Guide1.82,Revision0positionC.7,50$oftheeffective sumpareawasconsidered tobeblockedbyLOCAgenerated debris.Atthetimethattheplantwaslicensed, nodistinction wasdrawnbetweenthevariouspotential sourcesofpost-LOCA debris;thesesystemswereintendedtofunctionwithdebrisfromanysourcepartially obstructing thesumpsand50%blockagewasconsidered tobeaconservative estimateofpotential sumpblockage.

Theanalysesandmodeltestingresultssubmitted aspartofthelicensi'ng basisfortheplantdemonstrate, that,evenwith50%ofeffective sumpareablockage, theECCSandCTSwillcontinuetoprovidesufficient coolingflowtofulfillthelong-term coolingfunctions requiredtoconformwith10CFR50.46(b)(5).

Thecontainment recirculation sumpdesignwasmodel-tested attheAldenResearchLaboratories inthelate1970stoevaluateairentrainment andvortexing concerns.

Thesetestsdetermined thatthemodifications, asprescribed bya1978Aldenstudy,wouldbe.effective inassuringacceptable sumpperformance.

Additionally, empirical datafordetermining theheadlossatthesumpentrancewereobtainedforsumpblockages upto50%ofthescreenarea.

Attachment toAEP:NRC:C0599-01 Page7ThesetestresultsandNRCrequestsforsupplementary information

~weresubmitted totheNRCviareferences 2and3.TheNRCreviewedthetestresultsandthesupplementary information andissuedaSERdatedJuly2,1982.TheSERstatesinpart,"Basedontheapplicant's implementation ofthesumpmodifications asrecommended bytheSeptember 1978andDecember1979reportsandacceptable resultsreportedintheApril28,1982submittal, we-findthesetestsmeettheintentofapplicable portionsofRegulatory Guide1.68,1.79,and1.82,andaretherefore acceptable."

Theplant'slicensing basis,asacceptedbytheNRC,asdescribed intheSERprovidestheregulatory andsafetybasisfortheECCSandCTSsystems.Ourcoatingsarenottreatedasaseparatedebrissourceinthepreviously described licensing basis.Additionally, thesumpscreen50%blockageassumption doesnotdifferentiate betweenthesourcesfortheLOCAgenerated debris.SpecificResponsetoItem(2)(ii)(a)

Theplantdoesnotusecommercial gradecoatingsinsidecontainment forServiceLevel1applications.

References:

1.EPRITR-109937, "Guideline onNuclearSafety-Related Coatings,"

datedApril1998.2.LetterAEP:NRC:0112, J.Tillinghast toH.R.Denton,datedDecember20,1978.3.LetterAEP:NRC:0355A, "CONTAINMENT RECIRCULATION SUMPTEST,",datedApril28,1982.

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