ML17331B139
| ML17331B139 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/15/1993 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17331B140 | List: |
| References | |
| NUDOCS 9312270240 | |
| Download: ML17331B139 (7) | |
Text
ATTACHMENT3TOAEP:NRC:1166HMARKED-UPCOPIESOFTHEEXISTINGT/SPAGES9312270240931215PDRADOCK05000315PPDB CTOCOOSYSTEMSURVEILLANCESContinuedCo2.Tubesinthoseareas~hereexperiencehasindicatedpotentialproblems.3.h.tubeinspection(pursuanttoSpecification4.4.5.4.a.8)shallbeperformedoneachselectedtube..Ifanyselectedtubedoesnotpermitthepassageoftheeddycurrentprobeforatube~inspection,thisshallberecordedandanadjacenttubeshallbeselectedandsubjectedtoatubeinspection.Thetubesselectedasthesecondandthirdsamples(ifrequiredbyTable4.4>>2)duringeachinsezviceinspectionmaybesubjecte'dtoapartialtubeinspectionprovided:l.Thetubesselectedforthesamplesincludethetubesfromthoseareasofthetubesheetarraywheretubeswithimperfectionswerepreviouslyfound.d.2.Theinspectionsincludethos'epor'tionsofthetubeswhereimperfectionswerepreviouslyfound..l9"Implementationofthesteamgeneratortube/tubesuppplateinterimpluggingcriteriaforonefuelcycle(Cyclerequiresa100%bobbincoilinspectionforhot.legtubesupportplateintersectionsandcoldlegintersectionsdowntothelowestcoldlegtubesupportplatewithknownouterdiameterstress'corrosioncracking{ODSCC)indications.Theresultsofeachsampleinspectionshallbeclassifiedintooneofthefollowingthreecategories:CategoOIusectionResultsC-lLessthan5tofthetotaltubesinspectedaredegradedtubesandnoneoftheinspectedtubesaredefective.C-2Oneormoretubes,butnotmorethan1%ofthetotaltubesinspectedaredefective,orbetween5%and10%ofthetotaltubesinspectedaredegradedtubes.C-3Korethan10%ofthetotal.tubesinspectedaredegradedtubesormorethan1'toftheinspectedtubesaredefective.COOKNUCLEARPLANT-UNIT13/44-8AMENDMENTNO.M,454166 REACTORCOOSSTEMSSURVEILLANCUSCotuedaroundtheU-bendtothetopsupportofthecoldleg.Poratubeinwhichthetubesupportplateelevationinterim,plugginglimithasbeenapplied,theinspectionwillincludeallthehotlegintersectionsandall'oldlegintersectionsdownto,atleast,thelevelofthelastcrackindication.9.~aleevinataheispernitaedonlyinareasvherethesleevespansthetubesheetareaandwhoselowerjointisattheprimaryfluidtubesheetface.10.eTubeuortlatenterimPluinCriteriaisusedfordispositionofasteamgeneratortubeforcontinuedservicethatisexperiencingouterdiameterinitiatedstresscorrosioncrackingconfinedwithinthethicknessofthetubesupportplates.Porapplicationofthetubesupportplateinterimplugginglimit,thetube'sdispositionforcontinuedservicewillbebaseduponstandardbobbinprobesignalamplitude.Theplant-specificguidelinesusedforallinspectionsshall'eamendedasappropriatetoaccommodatetheadditionalinformationneededtoevaluatetubesupportplatesignalswithrespecttotheabovevoltage/depthparameters.PendingincorporationofthevoltageverificationrequirementinASMEstandardverifications,anASMEstandardcalibratedagainstthelaboratorystandardwillbeutili.redintheDonaldC.CookNuclearPlantUnit1steamgeneratorinspectionsforconsistentvoltagenormalization.1.Atubecanremaininserviceifthesignalamplitudeofacrackindicationislessthanorequalto1.0volt,regardlessofthedepthoftubewallpenetration,if,asaresult,theprojectedend-of-cycledistributionof"'rack.indicationsisverifiedtoresultin'rimary-to-secondaryleakagelessthan1gpminthefaultedloopduringapostulatedsteamlinebreakevent.ThemethodologyforcalculatingexpectedleakratesfromtheprojectedcrackdistributionmustbeconsistentwithVCAP-13187,Rev.0)(~85PgSi"AheQ1llJfgjjjPg/Q/gP/2.htubeshouldbepluggedorrepairedif,thesignalamplitudeofthecrackindicationisgreaterthan1.0voltexceptasnotedin4.4.5.4.a.10.3below.AMENDMENTNO.084541663/44-113.Atube.canremaininservicewithabobbincoilsignalamplitudegreaterthan1.0voltbutlessthanorequalZdlvoltsifarotatingpancakeprobeinspectiondoesnotdetectdegradation."Indicationsofdegiadationwithabobbincoilsignalamplitudegreaterthan.voltswillbepluggedorrepaired.~,lCOOKNUCLEARPLANT-UNIT1 0CGCNDRp3.4.6.2ReactorCoolantSystemleakageshallbelimitedto:a.NoPRESSUREBOUNDARYLEAKAGE,b.1GPHUNIDENTIFIEDLEAKAGE,c600gallonspezdaytotalpz-to-secondazyleakagethroughallsteamgeneratorsand150'nsperdaythroughanyonesteamgeneraeorforcruelCycled.10GPHIDENTIFIEDLE/QQLGEfromtheReactorCoolaneSystem,e.Seallineresistancegreaterthanorequalto2.27E-1ft/gpmiand,1GPHleakagefromanyreactorcoolantsystempressureisolationvalvespecifiedinTable3.4-0.AOTZON'ithanyPRESSUREBOUNDARYLEDGE;beinaeleaseHOTSTANDBYwithin6hoursandinCOLDSHUTDOWNwithinthefollowing30hours.b.WithanyReactorCoolantSystemleakagegreaterthananyoneoftheabovelimits,excludingPRESSUREBOUNDARYLEAKAGE,reducetheleakageratetowithinlimitswithin4hoursorbeinaeleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOQHwithinthefollowing30hours.CeKithanyreactorcoolanesystempressureisolationvalve(s)leakagegreaterthantheabovelimit,exceptwhen:I1.Theleakageislessthanorequalto5.0gpm,and2.Themostrecenemeasuredleakagedoesnoeexceedthepreviousmeasuredleakage*byanamountthatreducestheAHENDHENTNO.kent16joOrderdatedApril20,1981*TosatisfyhD8hraquiremenes,measuredleakagemaybemeasuredindirectly(asfromtheperformanceofpressureindicators)ifaccomplishedinaccordancewithapproved'roceduresand"supportedbycomputationsshowingthatthemethodiscapableofdemonstratingvalvecompliancewiththeleakagecriteria.Specifi.cation3.4.6.2.e.is-applicablewithaveragepressurewithin20.psiofthenominalfullpressurevalue.COOKNUCLEARPLANT-UNIT13/44-16 0C4.4,TheSurveillanceRequirementsforinspectionofthesteamgeneratortubasensurethaethastructuralintegrityofthisportionofeheRCSvillbemaintained.TheprogramforinsaxviceinspectionofsteamgenezatortubesisbasedonamodificationofRegulatoryGuide1.83,Revision1.Xnserviceinspe'ctionofsteamgeneratortubingisessentialQLordextomaintainsurveillanceoftheconditionsofthetubesinthaeventthatthereisevidenceofmechanicaldisagaorprogressivedegradationduetodesign,manufacturingerrors,orinserviceconditionsthatleadtocorrosion.Inservicainspectionofsteamgeneratortubingalsoprovidesa,means'ofcharacterizingthenaturaandcauseofanytubedegradationsothatcorrectivemeasux'escanbetaken.tqTheplaneisexpectedtobeoperatedinamannersuchthathesecond-arycoolantvillbemaintainedvithinthosechemistrylimitsoundtoresultinnegligiblecorrosionofthesteamgeneratortubes.Ifesecondarycoolanechemistryisnotmaintainedvithintheseparametecozrosionmaylikelyresultinstresscorrosioncrackingcrackingduringplantoperationvouldbelimitedbythegeneratortubeleakagebetveentheprimarycoolanesystcoolantsystem.Theallovableprimary-to-secondarylelimits,localizedTheextentofimitationofsteamandthesecondaryrateis150gallonsperdayperseeamgeneratorforonefuelcycle(Cycle.Axialorcizcumferentiallyorientedcrackshavingaprimary-to-secondaryleakagelessthanthislimitduringoperationvillhaveanadequatemarginofsafetytovithstandeheloadsimposedduringnormaloperationandbypostulatedaccidents.Leakageinexcessofthislimitvillrequireplaneshutdovnandaninspection,duringvhichtheleakingtubesvillbelocatedandpluggedorrepaired.AsteamgeneratorvhileundergoingcreviceflushinginNode4isavailablefordecayheatremovalandisoperable/opexaeinguponreinstatementofaux'.iazyormainfeedflovcontrolandsteamcontrol.wastage-typedefectsaraunlikelyviththeallvolatQ.etreatment(AVT)ofsecondarycoolant.Hovevex',evenifadefectofsimilartypeshoulddevelopinservice,itvillbefoundduringscheduledinsenricasteamgeneratortubeexanixmtions.Pluggingorsleevtngvillberequiredforalltubesvithimperfectionsexceedingtherepairlimitvhich,isdefinedinSpecification4.4.5.4.a.Steamgeneratortubeinspectionsofoperatingplantshavedemonsezatadthecapabilitytoreliablydetectdegzadaeionthathaspenetrated20%oftheoriginaltubevalithickness.Tubesexperiencingouterdiameterstresscorrosionczackingvithinehethicknessofthetubesupportplatesarapluggedorrepairedbythecriteriaof4.4.5.4.a.lO.COOKNUCLEARPLANT-UNIT1B3/44<<2ahHEH".":~NO.~444166 C0C0HaSntaininganoperating1gelimitof150gpdpersteamgenerator(600gpdtotal)forPuelCyclevillminimi=ethepotentialfox'largeleakageeventduzingsteamlinereaRunderLOCAconditions.BasedontheNDEuncertainties,bobbincoilvoltagedistributionandcrackgrovthratefromthepreviousinspection,theexpectedleakratefollovingasteamlineruptureislimitedtobelov120gpminthefaultedloopand150gpdpersteamgeneratorIntheintactloops,vhichvilllimitoffsitedosestovithin10percentofthe10CPR100guidelines.Ifthepro)ectedendofcycledistzibutionofczackindicationsresultsInprimary-to-secondaryleakagegreaterthan120gpminthefaultedloopduringapostulatedsteamlinebreakevent,additionaltubesmustbaremovedfromserviceinordertoreducethepostulatedprimary-to-secondazysteamlinebreakleakagetobelov120gpm.PRESSUREBOUNDARYLEAKAGEofanymagnitudeisunacceptablesinceitmaybeindicativeofanImpendinggrossfailureofthepressureboundary.ShouldPRESSUREBOUNDARYUMQLGEoccuzthroughacomponentvhichcanbeisolatedfromthebalanceoftheReactorCoolantSystem,plantoperationmaycontinueprovidedtheleakingcomponentispromptlyisolatedfromtheReactorCoolantSystemsinceisolationremovesthesouxcaofpotentialfailure.TheSurveillanceRequIrementsforRCSPressureXsolationValvesprovideaddedassuranceofvalveintegritytherebyreducingtheprobabilityofgrossvalvefailureandconsequentintersystemLOCA.LeakagefromtheRCSPressureIsolationValvesisZDENTXPXEDLEAKAGEandvillbeconsideredasaportionofthealloved11mit.34.4.7CKBfISTRYThelimitationsonReactorCoolantSyst~chemistryensurethatcorrosionoftheReactorCoolantSystemisminimizedandreducesthepotentialforReactorCoolantSystemleakageorfailureduetostresscorrosion.maintainingthechemistryvithintheSteadyStateLimitsprovidesadequatecorrosionprotectiontoensuzethestructuralintegrityoftheReactorCoolantSystemoveithelifeoftheplant.Theassociatedeffectsofexceedingtheoxygen,chloride,andfluoridelimitsare'timeandtemperaturedependent.Corrosionstudiesshovthatoperationmay'econtinuedvithcontaminantconcentrationlevelsinexcessoftheSteadyStateLimits,uptotheTransientLimits,foxthespecifiedlimitedtimeintervalsvithouthavingasignIficanteffectonthestructuralintegrityoftheReactorCoolantSystem.ThetimeIntervalpermittingcontinuedoperationvithintherestrictionsoftheTransientLimitsprovidestimefortakingcorrectiveactIonstorestorethecontaminantconcentrationstovithintheSteadyStateLimits.COOKNUCLEARPLANT-UHXT1B3/44-4hHEHDHZNTNOM166.
ATTACHMENT4TOAEP:NRC:1166HPROPOSEDREVISEDT/SPAGES