ML17331A091

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Proposed Tech Specs Supporting Request to Allow Interim Plugging Criteria of 1.0 Volt for Cycle 14
ML17331A091
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Site: Cook American Electric Power icon.png
Issue date: 03/10/1993
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
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ML17331A090 List:
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NUDOCS 9303160110
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ATTACHMENT 3toAEP:NRC:1166G PROPOSEDREVISEDTECHNICAL SPECIFICATIONS PAGES9303i601ip 9303i0PDRADQCK'50003i 5P,'DR REACTORCOOLANTSYSTEMSURVEILLANCE REUIREMENTS Continued Tubesinthoseareaswhereexperience hasindicated potential problems.

Atubeinspection (pursuant toSpecification 4.4.5.4.a.8) shallbeperformed oneachselectedtube.Ifanyselectedtubedoesnotpermitthepassageoftheeddycurrentprobeforatubeinspection, thisshallberecordedandanadjacenttubeshallbeselectedandsubjected toatubeinspection.

c.Thetubesselectedasthesecond'andthirdsamples(ifrequiredbyTable4.4-2)duringeachinservice inspection maybesubjected toapartialtubeinspection provided:

Thetubesselectedforthesamplesincludethetubesfromthoseareasofthetubesheetarraywheretubeswithimperfections werepreviously found.d.2:Theinspections includethoseportionsofthetubeswhereimperfections werepreviously found.Implementation ofthesteamgenerator tube/tube supportplateinterimpluggingcriteriaforonefuelcycle(Cycle14)requiresa100Xbobbincoilinspection forhotlegtubesupportplateintersections andcoldlegintersections downtothelowestcoldlegtubesupportplatewithknownouterdiameterstresscorrosion cracking(ODSCC)indications.

Theresultsofeachsampleinspection shallbeclassified intooneofthefollowing threecategories:

CaterInsectionResultsC-lLessthan5Xofthetotaltubesinspected aredegradedtubesandnoneoftheinspected tubesaredefective.

C-2Oneormoretubes,butnotmorethan1Xofthetotaltubesinspected aredefective, orbetween5Xand10Xofthetotaltubesinspected aredegradedtubes.C-3iMorethan10Xofthetotaltubesinspected aredegradedtubesormorethan1Xoftheinspected tubesaredefective.

COOKNUCLEARPLANT-UNIT13/44-8AMENDMENT NO.%3,~~

REACTORCOOLANTSYSTEMOPERATIONAL LEAKAGELIMITINGCONDITION FOROPERATION 3.4.6.2ReactorCoolantSystemleakageshallbelimitedto:a.NoPRESSUREBOUNDARYLEAKAGE,b.1GPMUNIDENTIFIED LEAKAGE,c~600gallonsperdaytotalprimary-to-secondary leakagethroughallsteamgenerators and150gallonsperdaythroughanyonesteamgenerator forFuelCycle14.d.10GPMIDENTIFIED LEAKAGEfromtheReactorCoolantSystem,e.Seallineresistance greaterthanorequalto2.27E-lft/gpm~and,f.1GPMleakagefromanyreactorcoolantsystempressureisolation valvespecified inTable3.4-0.APPLICABILITY:

MODES1,2,3and4.~ACTION'~WithanyPRESSUREBOUNDARYLEAKAGE,beinatleastHOTSTANDBYwithin6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.b.WithanyReactorCoolantSystemleakagegreaterthananyoneoftheabovelimits,excluding PRESSUREBOUNDARYLEAKAGE,reducetheleakageratetowithinlimitswithin4hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.c~Withanyreactorcoolantsystempressureisolation valve(s)leakagegreaterthantheabovelimit,exceptwhen:Theleakageislessthanorequalto5.0gpm,and2.Themostrecentmeasuredleakagedoesnotexceedthepreviousmeasuredleakage*byanamountthatreducestheTosatisfyALARArequirements, measuredleakagemaybemeasuredindirectly (asfromtheperformance ofpressureindicators) ifaccomplished inaccordance withapprovedprocedures andsupported bycomputations showingthatthemethodiscapableofdemonstrating valvecompliance withtheleakagecriteria.

Specification-3.4:6.2.e isapplicable withaveragepressurewithin20psiofthenominalfullpressurevalue.COOKNUCLEARPLANT-UNIT13/44-16Amendment No.+62-466-OrderdatedApril20,1981

\~C~

EACTORCOOLANTSYSTEM~ASES3445STEAMGENERATORS TUBEINTEGRTheSurveillance Requirements forinspection ofthesteamgenerator tubesensurethatthestructural integzity ofthisportionoftheRCSwillbemaintained.

Theprogramforinservice inspection ofsteamgenerator tubesisbasedonamodification ofRegulatory Guide1.83,Revisionl.Inservice

-inspection ofsteamgenerator tubingisessential inordertomaintainsuzveillance oftheconditions ofthetubesintheeventthat:thereisevidenceofmechanical damageorprogressive degradation duetodesign,manufacturing errors,orinservice conditions thatleadtocorrosion.

Insezvtce inspection ofsteamgenerator tubingalsoprovidesameansofcharacterizing thenatureandcauseof.anytubedegradation sothatcorrective measurescanbetaken.Theplantisexpectedtobeoperatedinamannersuchthatthesecond-arycoolantwillbemaintained withinthosechemistry limitsfoundtoresult:innegligible corrosion ofthesteamgenerator tubes.Xfthesecondary coolantchemistry isnotmaint:ained withintheseparameter limits,localized corrosion maylikelyresultinstresscorrosion cracking.

Theextentofcrackingduringplantoperation wouldbelimitedbythelimitation ofsteamgenerator tubeleakagebetweentheprimarycoolantsystemand.thesecondary coolantsystem.Theallowable primary-to-secondary leakrateis150gallonsperdaypersteamgenerator foronefuelcycle(Cycle14).Axialorcircumferentially orientedcrackshavingaprimary-to-secondary leakagelessthanthislimit:duringoperation willhaveanadequatemarginofsafetytowithstand t:heloadsimposedduringnormaloperation andbypostulated accidents.

Leakageinexcessofthislimitwillrequireplantshutdownandaninspection, duringwhichtheleakingtubeswillbelocatedandpluggedorrepaired.

Asteamgenerator whileundergoing creviceflushinginMode4isavailable fordecayheatremovalandisoperable/

operating uponreinstatement ofauxiliary ormainfeedflowcontrolandsteamcontrol.Wastage-type defectsareunlikelywiththeallvolatiletreatment (AVT)ofsecondary coolant.However,evenifadefect:ofsimilartypeshoulddevelopinservice,itwillbefoundduringscheduled inservice st:earngenerator tubeexaminations.

Pluggingorsleevingwillberequiredforalltubeswithimperfections exceeding therepairlimitwhichisdefinedinSpecification 4.4.5.4.a.

Steamgenerator tubeinspections ofoperating plantshavedemonst:rated thecapability toreliablydetectdegradation thathaspenetrated 20Xoftheoriginaltubewallthickness.

Tubesexpeziencing outerdiameterstresscorrosion crackingwithinthethickness ofthetubesupportarepluggedorrepairedbythecriteriaof4.4.5.4.a.10, COOKNUCLEARPLANT-UNIT1B3/44-2aAMENDMENT NO.403,~

EACTORCOOLANSYSTBASESMaintaining anoperating leakagelimitof150gpdpersteamgenerator (600gpdtotal)forFuelCycle14willminimizethepotential foralargeleakageeventduringsteamlinebreakunderLOCAconditions.

BasedontheNDEuncertainti.es, bobbincoilvoltagedistribution andcrackgrowthratefromthepreviousinspection, theexpectedleakratefollowing asteamlineruptureislimitedtobelow120gpminthefaultedloopand150gpdpersteamgenerator intheintactloops,whichwilllimitoffsitedosestowithin10percentofthe10CFR100guidelines.

Iftheprojected endofcycledistribution ofcrakindications resultsinprimary-to-secondazy leakagegreaterthan120gpminthefaultedloopduringapostulated steamlinebreakevent,additional tubesmustberemovedfromserviceinordertoreducethepostulated primary-to-secondary steamlinebreakleakagetobelow120gpm.PRESSUREBOUNDARYLEAKAGEofanymagnitude isunacceptable sinceitmaybeindicative ofanimpending grossfailureofthepressureboundary.

ShouldPRESSUREBOUNDARYLFAKAGEoccurthroughacomponent whichcanbeisolatedfromthebalanceoftheReactorCoolantSystem,plantoperati.on maycontinueprovidedtheleakingcomponent ispromptlyisolatedfromtheReactorCoolantSystemsinceisolation removesthesourceofpotential failure.TheSurveillance Requirements forRCSPressureIsolation Valvesprovideaddedassurance ofvalveintegrity therebyreducingtheprobability ofgrossvalvefailureandconsequent intersystem LOCA.LeakagefromtheRCSPressureIsolation ValvesisIDENTIFIED LEAKAGEandwillbeconsidered asaportionoftheallowedlimit.344CHEMISTRY Thelimitations onReactorCoolantSystemchemistry ensurethatcorrosion oftheReactorCoolantSystemisminimized andreducesthepotential forReactorCoolantSystemleakageorfailureduetostresscorrosion.

Maintaining.

thechemistry withintheSteadyStateLimitsprovidesadequatecorrosion protection toensurethestructural integrity oftheReactorCoolantSystemoverthelifeoftheplant.Theassociated effectsofexceeding theoxygen,chloride, andfluoridelimitsaretimeandtemperature dependent.

Corrosion studiesshowthatoperati,on maybecontinued withcontaminant concentration levelsinexcessoftheSteadyStateLimits,uptotheTransient Limits,forthespecified limitedtimeintervals withouthavingasignificant effectonthestructural integrity oftheReactorCoolantSystem.Thetimeintervalpermi,tting continued operation withintherestrictions oftheTransi.ent Limitsprovidestimefortakingcorrective actionstorestorethecontaminant concentrations towithintheSteadyStateLimits.COOKNUCLEARPLANT-UNIT1B3/44-4AMENDMENT NO.~~

ATTACHMENT 4toAEP:NRC:1166G CURRENTPAGESMARKED-UP TOREFLECTPROPOSEDCHANGES CTOCOOLANSEHSURILLANCEIREMESContinued 2.Tubesinthoseareaswhereexperience hasindicated potential problems.

Atubeinspection (pursuant toSpecification 4.4.5.4.a.8) shallbeperformed oneachselectedtube.Ifanyselectedtubedoesnotpermitthepassageoftheeddycurrentprobeforatubeinspection, thisshallberecordedandanad5acenttubeshallbeselectedandsub]ected toatubeinspection.

c.Thetubesselectedasthesecondandthirdsamples(ifrequiredbyTable4.4-2)duringeachinsezvice inspection maybesub]ected toapartialtubeinspection provided:

1.Thetubesselectedforthesamplesincludethetubesfromthoseareasofthetubesheetarraywheretubeswithimperfections werepreviously found.2,Theinspections includethoseportionsofthetubeswhereimperfections werepreviously found.H"'.Implementation ofthesteamgenerator tube/tube suppplateinterimpluggingcriteriaforonefuelcycle(Cycle'equiresa100'tbobbincoilinspection forhot.legtubesupportplateintersections andcoldlegintersections downtothelowestcoldlegtubesupportplatewithKnownouterdiameterstresscorrosion cracking(ODSCC)indications.

Theresultsofeachsampleinspection shallbeclassified intooneofthefollowing threecategories:

CategoOInsectionResultsC-lLessthan5tofthetotaltubesinspected aredegradedtubesandnoneoftheinspected tubesaredefective.

C-2Oneormoretubes,butnotmorethan1%ofthetotaltubesinspected aredefective, orbetween5%and10%ofthetotaltubesinspected aredegradedtubes.C-3Morethan10%ofthetotaltubesInspected aredegradedtubesormorethan1%oftheinspected tubesaredefective.

COOKNUCLEARPLANT-UNIT13/44-8AMENDMENT NO.O8,454166 0GC3.4.6.2ReactorCoolantSystemleakageshallbelimitedto:a.NoPRESSUREBOUNDARYLEAKAGE,b.C~IGPEmIDEETZEZED

IEliEAGE, 600gallonspezdaytotalpzry-to-secondazy leakagethroughallsteamgenerators and150onsperdaythroughanyonesteamgenerator forFuelCyclePd.e.10GPEIDENTIFIED LEDGEfromtheReactorCoolantSystem,Seallineresistance greaterthanozequalto2.27E-lft/gpm~and,f.1GPNleakagefromanyreactorcoolantsystempressureisolation valvespecified inTable3.4-0.AOTZOE'ith anyPRESSUREBOUNDARYLEAKAGE;beinatleastHOTSTANDBYwithin6hoursandinCOLDSHUTDOWNwithinthefollowing 30houzs.b.WithanyReactorCoolantSystemleakagegreaterthananyoneoftheabo~elimits,excluding PRESSUREBOUNDARYIKKAGE,reducetheleakageratetowithinlimitswithin4hoursozbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.C~Withanyreactorcoolantsystempressureisolation valve(s)leakagegreaterthantheabovelimit,exceptwhen:l.Theleakageislessthanorequalto5.0gpm,and2.Themostrecentmeasuredleakagedoesnotexceedthepreviousmeasuredleakage*byanamountthatreducestheTosatisfy~iRArequirements, measuredleakagemaybemeasuredindirectly (asfromtheperformance ofpressureindicators) ifaccomplished inaccordance withapprovedprocedures andsupported bycomputations showingthatthemethodiscapableofdemonstrating valvecompliance withtheleakagecriteria.

Specification 3.4.6.2.e isapplicable withaveragepzessure-within 20.psiofthenominalfullpressurevalue.COOKNUCLEARPLANT-UNIT13/44-16AMENDMENT NO.444166OrderdatedApril20,1981 4.4TheSurveillance Requirements forinspection ofthesteamgenerator tubesensurethatthestructural integrity ofthisportionoftheRCSwillbemaintained.

Theprogramforinservice inspection ofsteamgenerator tubesisbasedonamodification ofRegulatory Guide1.83,Revisionl.Inservice inspection ofsteamgenerator tubingisessential inordertomaintainsurveillance oftheconditions ofthetubesintheeventthatthereisevidenceofmechanical damageorprogressive degradation duetodesign,manufacturing errors,orinservice conditions thatleadtocorrosion.

Inservice inspection ofsteamgenerator tubingalsoprovidesameansofcharacterizing thenatureandcauseofanytubedegradation sothatcorrective measurescanbetaken.Theplantisexpectedtobeoperatedinamannersuchthathesecond-arycoolantwillbemaintained withinthosechemistry limitsoundtoresultinnegligible corrosion ofthesteamgenerator tubes.Ifesecondary coolantchemistry isnotmaintained withintheseparametelimits,localized corrosion maylikelyresultinstresscorrosion crackingTheextentofcrackingduringplantoperation wouldbelimitedbytheimitation ofsteamgenerator tubeleakagebetweentheprimarycoolantsystandthesecondary coolantsystem.Theallowable primary-to-secondary lerareis150gallonsperdaypersteamgenerator foronefuelcycle(Cycle.Axialorcircumferentially orientedczackshavingaprimary-to-secondary leakagelessthanthislimitduringoperation willhaveanadequatemarginofsafetytowithstand theloadsimposedduringnormaloperation andbypostulated accidents.

Leakageinexcessofthislimitwillrequireplantshutdownandaninspection, duringwhichtheleakingtubeswillbelocatedandpluggedorrepaired.

Asteamgenerator whileundergoing creviceflushinginMode4isavailable fordecayheatremovalandisoperable/operating uponreinstatement ofauxiliary ormainfeedflowcontzolandsteamcontrol.Wastage-type defectsazeunlikelywiththeallvolatQ.etreatment (AVT)ofsecondary coolant.However,evenifadefectofsimilartypeshoulddevelopinservice,itwillbefoundduringscheduled insezvice steamgenerator tubeexaminations.

Pluggingorsleevtngwillberequiredforalltubeswithimperfections exceeding therepairlimitwhichisdefinedinSpecification 4.4.5.4.a.

Steamgenerator tubeinspections ofoperating planeshavedemonstrated thecapability toreliablydetectdegradation thathaspenetrated 20%oftheoriginaltubewallthickness.

Tubesexperiencing outerdiameterstresscorrosion crackingwithinthethickness ofthetubesupportplatesarepluggedorrepairedbythecriteriaof4.4.5.4.a.10.

COOKNUCLEARPLANT"UNIT1B3/44-2aAMENDMENT NO.~~166 s'.0COCOrXhZZMaintaining anoperating 1gelimitof150gpdpersteamgenerator (600gpdtotal)forFuelCyclewillminimizethepotential foralargeleakageeventduringsteamlinereekunderLOCAconditions.

BasedontheNDEuncertainties, bobbincoilvoltagedistribution andcrackgrowthratefromthepreviousinspection, theexpectedleakratefollowing asteamlineruptureislimitedtobelow120gpminthefaultedloopand150gpdpersteamgenerator intheintactloops,whichwilll~toffsitedosestowithin10percentofthe10CFR100guidelines.

Iftheprojected endofcycledistribution ofcrackindications resultsinprimary-to-secondary leakagegreaterthan120gpminthefaultedloopduringapostulated steamlinebreakevent,additional tubesmustberemovedfromserviceinordertoreducethepostulated primary-to-secondary steamlinebreakleakagetobelow120gpm.PRESSUREBOUNDARYLEAKAGEofanymagnitude isunacceptable sinceitmaybeindicative ofanimpending grossfailureofthepressureboundary.

ShouldPRESSUREBOUNDARYLEAKAGEoccurthroughacomponent whichcanbeisolatedfromthebalanceoftheReactorCoolantSystem,plantoperation maycontinueprovidedtheleakingcomponent ispromptlyisolatedfromtheReactorCoolantSystemsinceisolation removesthesourceofpotential failure.IITheSurveillance Requirements fozRCSPressureIsolation Valvesprovideaddedassurance ofvalveintegrity therebyreducingtheprobability ofgrossvalvefailureandconsequent intersystem LOCA.LeakagefromtheRCSPressureIsolation ValvesisIDENTIFIED LEAKAGEandwillbeconsidered asaportionoftheallowedlimit./34.4.7KiEMISTRY Thelimitations onReactorCoolantSystemchemistry ensurethatcorrosion oftheReactorCoolantSystemisminimiedandreducesthepotential forReactorCoolantSystemleakageorfailureduetostresscorrosion.

Haintaining thechemistry withintheSteadyStateLimitsprovidesadequatecorrosion protection toensurethestzuctural integrity oftheReactorCoolantSystemoverthelifeoftheplant.Theassociated effectsofexceeding theoxygen,chloride, andfluoridelimitsaretimeandtemperature dependent.

Corrosion studiesshowthatoperation maybecontinued withcontaminant concentration levelsinexcessoftheSteadyStateLimits,uptotheTransient Limits,forthespecified limitedtimeintervals withouthavingasignificant effectonthestructural integrity oftheReactorCoolantSystem.Thetimeintervalpermitting continued operation withintherestrictions oftheTransient Limitsprovidestimefortakingcorrective actionstorestorethecontaminant concentrations towithintheSteadyStateLimits.COOKNUCLEARPLANT-UNIT1B3/44-4hK?HDHENT NOM6 t.l~~IOlgg,C,S!Ilt'4j~e4

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