ML17329A422

From kanterella
Revision as of 07:38, 29 June 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Proposed Tech Specs Re Plugging Criteria for SG Tubes
ML17329A422
Person / Time
Site: Cook 
Issue date: 03/20/1992
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17329A421 List:
References
NUDOCS 9203260130
Download: ML17329A422 (32)
v • d • e


Text

ATTACHMENT 2toAEP:NRC:1166 PROPOSEDREVISEDTECHNICAL SPECIFICATIONS PAGES9203260130 920320PDRADOCK050003l5PDR LIGCONDITION FOOPERAT03.4.5Eachsteamgenerator shallbeOPERABLE.

APPLICABILITY:

MODES1,2,3and4.*ACTION:Withoneormoresteamgenerators inoperable, restoretheinoperable generator(s) toOPERABLEstatuspriortoincreasing T,~above200F.0SURVEILLANCE REUIREMENTS 4.4.5.0Eachsteamgenerator shallbedemonstrated OPERABLEbyperformance ofthefollowing augmented inservice inspection programandtherequirement ofSpecification 4.0'.4.4.5.1SteamGenerator SamleSelection aInsectio-Eachsteamgenerator shallbedetermined OPERABLEduringshutdownbyselecting andinspecting atleasttheminimumnumberofsteamgenerators specified inTable4.4-1.4.4.5.2SteamGenerator TubeSamleSelectioandInsectio-Thesteamgenerator tubeminimumsamplesize,inspection resultclassification, andthecorresponding actionrequiredshallbeasspecified inTable4.4-2.Theinservice inspection ofsteamgenerator tubesshallbeperformed atthefrequencies specified inSpecification 4.4.5.3andtheinspected tubesshallbeverifiedacceptable pertheacceptance criteriaofSpecification 4.4.5.4.Thetubesselectedforeachinservice inspection shallincludeatleast3%ofthetotalnumberoftubesinallsteamgenerators'the tubesselectedfortheseinspections shallbeselectedonarandombasisexcept:Ia.Whereexperience insimilarplantswithsimilarwaterchemistry indicates criticalareastobeinspected, thenatleast50%ofthetubesinspected shallbefromthesecriticalareas.b.Thefirstsampleoftubesselectedforeachinservice inspection (subsequent tothepreservice inspection) ofeachsteamgenerator shallinclude:1.Alltubesthatpreviously haddetectable wallpenetrations (greaterthanorequalto20%)thathavenotbeenpluggedorrepairedbysleevingintheaffectedarea.*ThisSpecification doesnotapplyinMode4whileperforming creviceflushingaslongasLimitingConditions forOperation forSpecification 3.4.1.3aremaintained.

COOKNUCLEARPLANTUNIT13/44-7AMENDMENT NO.

COCOSYSSURVEILLANCE REUIREMENTS Continud2.Tubesinthoseareaswhereexperience hasindicated potential problems.

3.Atubeinspection (pursuant toSpecification 4.4.5.4.a.8) shallbeperformed oneachselectedtube.Ifanyselectedtubedoesnotpermitthepassageoftheeddycurrentprobeforatubeinspection,'his shallberecordedandanadjacenttubeshallbeselectedandsubjected toatubeinspection.

c.Thetubesselectedasthesecondandthirdsamples(ifrequiredbyTable4.4-2)duringeachinservice inspection maybesubjected toapartialtubeinspection provided:

1.Thetubesselectedforthesamplesincludethetubesfromthoseareasofthetubesheetarraywheretubeswithimperfections werepreviously found.2.Theinspections includethoseportionsofthetubeswhereimperfections werepreviously found.Implementation ofthesteamgenerator tube/tube supportplatealternate pluggingcriteriarequiresa100$bobbinprobeinspection forhotlegtubesupportplateintersections andcoldlegintersections downtothelowestcoldlegtubesupportplatewithknownouterdiameterstresscorrosion cracking(ODSCC)indications.

Aninspection usingtherotatingpancakecoil(RPC)probeisrequiredforalltubesupportplateintersection indications forbobbincoilsignalamplitude between1.5and4.0voltsprovidedthetubeistobeleftinservice.TheRPCresultsaretobeevaluated toestablish thattheprincipal indications canbecharacterized asODSCC.Onceanindication ischaracterized asODSCC,RPCinspections willbeperformed onthisindication atalternate subsequent refueling outages.Fortubesthatwillbeadministratively plugged,noRPCinspection isrequired.

Theresultsofeachsampleinspection shallbeclassified intooneofthefollowing threecategories:

~Cate~oryInsectionesultsC-1Lessthan5%ofthetotaltubesinspected aredegradedtubesandnoneoftheinspected tubesaredefective.

C-2Oneormoretubes,butnotmorethan1%ofthetotaltubesinspected aredefective,,or between5%and10%ofthetotaltubesinspected aredegradedtubes.C-3AMENDMENT NO.QS,444Morethan10%ofthetotaltubesinspected aredegradedtubesormorethan1%oftheinspected tubesaredefective..

COOKNUCLEARPLANT-UNIT13/44-8 SouNote:Inallinspections, previously degradedtubesmustexhibitsignificant (greaterthanorequalto10%)furtherwallpenetrations tobeincludedintheabovepercentage calculations.

4.4.5.3InsectionFreuencies-Theaboverequiredinservice inspections ofsteamgenerator tubesshallbeperformed atthefollowing frequencies:

Thefirstinservice inspection shallbeperformed after6Effective FullPowerMonthsbutwithin24calendarmonthsofinitialcriticality.

Subsequent inservice inspections shallbeperformed atintervals ofnotlessthan12ormorethan24calendarmonthsafterthepreviousinspection.

Iftwoconsecutive inspections following serviceunderAVTconditions, notincluding thepreservice inspection, resultinallinspection resultsfallingintotheC-lcategoryoriftwoconsecutive inspections demonstrate thatpreviously observeddegradation hasnotcontinued andnoadditional degradation hasoccurred, theinspection intervalmaybeextendedtoamaximumofonceper40months.b.Iftheresultsofinservice inspection ofasteamgenerator conducted inaccordance withTable4'-2at40monthintervals fallinCategoryC-3,theinspection frequency shallbeincreased toatleastonceper20months.Theincreaseininspection frequency shallapplyuntilthesubsequent inspections satisfythecriteriaofSpecification 4.4.5.3.a; theintervalmaythenbeextendedtoamaximumofonceper40months,Additional, unscheduled inservice inspections shallbeperformed oneachsteamgenerator inaccordance withthefirstsampleinspection specified inTable4.4-2duringtheshutdownsubsequent toanyofthefollowing conditions:

1.Primary-to-secondary tubesleaks(notincluding leaksoriginating fromtube-to-tube sheetwelds)inexcessofthelimitsofSpecification 3.4.6.2.2.Aseismicoccurrence greaterthantheOperating BasisEarthquake.

3.Aloss-of-coolant accidentrequiring actuation oftheengineered safeguards.

4.Amainsteamlineorfeedwater linebreak.d.Tubesleftinserviceasaresultofapplication ofthetubesupportplatealternate pluggingcriteriashallbeinspected bybobbincoilprobeduringallfuturerefueling outages.COOKNUCLEARPLANT-UNIT13/44-9AMENDMENT NO.Q8 SSTSVCRIREMENTSCotnued4.4.5.4aceCritea~AsusedinthisSpecification:

contourofatubeorsleevefromthatrequiredbyfabrication drawingsorspecifications'ddy-current testingindications below20%ofthenominalwallthickness, ifdetectable, maybeconsidered asimperfections.

2.generalcorrosion occurring oneitherinsideoroutsideofatubeorsleeve.DeradedTubeorSleevemeansanimperfection greaterthanorequalto20%ofthenominalwallthickness causedbydegradation.

PercentDeradatiomeanstheamountofthewallthickness affectedorremovedbydegradation.

5.Defectmeansanimperfection ofsuchseveritythatitexceedstherepairlimit.ReairPluinLmitmeanstheimperfection depthatorbeyondwhichthetubeorsleevedtubeshallberepairedorremovedfromservice.Anytubewhich,uponinspection, exhibitstubewalldegradation of40percentormoreofthenominaltubewallthickness shallbepluggedorrepairedpriortoreturning thesteamgenerator toservice.Anysleevewhich,uponinspection, exhibitswalldegradation of29percentormoreofthenominalwallthickness shallbepluggedpriortoreturning thesteamgenerator toservice.Inaddition, anysleeveexhibiting anymeasurable walllossinsleeveexpansion transition orweldzonesshallbeplugged,Thisdefinition doesnotapplyfortubesexperiencing outerdiameterstresscorrosion crackingconfirmed bybobbinprobeinspection tobewithinthethickness ofthetubesupportplates.See4.4.5.4.a.10 fortheplugginglimitforusewithinthethickness ofthetubesupportplate.7.Unserviceable describes thecondition ofatubeorsleeveifitleaksorcontainsadefectlargeenoughtoaffectitsstructural integrity intheeventofanOperating BasisEarthquake, aloss-of-coolant

accident, orasteamlineorfeedwater linebreakasspecified in4.4.5.3.c, above.8.orsleevefromthepointofentry(hotlegside)completely COOKNUCLEARPLANT-UNIT13/44-10AMENDMENT NO.08,444 CtuaroundtheU-bendtothetopsupportofthecoldleg.Fora,tubeinwhichthetubesupportplateelevation alternate plugginglimithasbeenapplied,theinspection willincludeallthehotlegintersections andallcoldlegintersections downto,atleast,thelevelofthelastcrackindication.

9.~sleevlnatubeispermitted onlyinareaswherethesleevespansthetubesheet areaandwhoselowerjointisattheprimaryfluidtubesheet face.10.uisusedfordisposition ofasteamgenerator tubeforcontinued servicethatisexperiencing outerdiameterinitiated stresscorrosion crackingconfinedwithinthethickness ofthetubesupportplates.Forapplication ofthetubesupportplatealternate plugginglimit,thetube'sdisposition forcontinued servicewillbebaseduponstandardbobbinprobesignalamplitude.

Theplantspecificguidelines usedforallinspections shallbeamendedasappropriate toaccommodate theadditional information neededtoevaluatetubesupportplatesignalswithrespecttotheabovevoltage/depth parameters.

Pendingincorporation ofthevoltageverification requirement inASMEstandardverifications, anASMEstandardcalibrated againstthelaboratory standardwillbeutilizedintheDonaldC.CookNuclearPlantUnit1steamgenerator inspections forconsistent voltagenormalization.

1.Atubecanremaininserviceifthesignalamplitude ofacrackindication islessthanorequalto4.0volts,regardless ofthedepthoftubewallpenetration, if,asaresult,theprojected end-of-cycle distribution ofcrackindications isverifiedtoresultinprimary-to-secondary leakagelessthan120gpminthefaultedloopduringapostulated steamlinebreakevent.Themethodology forcalculating expectedleakratesfromtheprojected crackdistribution mustbeconsistent withWCAP-13187, Rev.0.2.Atubeshouldbepluggedorrepairedifthesignalamplitude ofthecrackindication isgreaterthan4.0volts.b.Thesteamgenerator shallbedetermined OPERABLEaftercompleting thecorresponding actions(plugging orsleevingalltubesexceeding therepairlimitandalltubescontaining through-wall cracks)requiredbyTable4.4-2.c.Steamgenerator tuberepairsmaybemadeinaccordance withthemethodsdescribed ineitherWCAP-12623 orCEN-313-P.

COOKNUCLEARPLANT-UNIT13/44-11AMENDMENT NO.98, REACTOR-COOSYSSVLIR4.4.5.5/eeocaeFollowing eachinservice inspection ofsteamgenerator tubes,ifthereareanytubesrequiring pluggingorsleeving, thenumberoftubespluggedorsleevedineachsteamgenerator shallbereportedtotheCommission within15days.b.Thecompleteresultsofthesteamgenerator tube,inservice inspection shallbeincludedintheAnnualOperating Reportfortheperiodinwhichthisinspection wascompleted.

Thisreportshallinclude:1,Numberandextentoftubesinspected.

2.Locationandpercentofwall-thickness penetration foreachindication ofanimperfection.

3.Identification oftubespluggedorsleeved.C.Resultsofsteamgenerator tubeinspections whichfallintoCategoryC-3andrequirepromptnotification oftheCommission shallbereportedpursuanttoSpecification 6.9.1priortoresumption ofplantoperation.

Thewrittenfollowupofthisreportshallprovideadescription ofinvestigations conducted todetermine causeofthetubedegradation andcorrective measurestakentopreventrecurrence.

d.Theresultsofinspections performed under4.4.5.2foralltubesinwhichthetubesupportplatealternate pluggingcriteriahasbeenappliedshallbereportedtotheCommission within15daysfollowing theinspection.

Thereportshallinclude:1.Listingofapplicable tubes.2.Location(applicable intersections pertube)andextentofdegradation (voltage).

COOKNUCLEARPLANT-UNIT13/44-12AMENDMENT NO.88,444 TABLE44-1MINIMUMNUMBEROFSTEAMGENERATORS TOBEINSPECTED DURINGINSERVICE INSPECTION Preservice Inspection No.ofSteamGenerators perUnitFirstInservice Inspection Second&Subsequent Inservice Inspections YesFourTwoOne~TableNotation:

1.Theinservice inspection maybelimitedtoonesteamgenerator onarotatingscheduleencompassing 3N%ofthetubes(whereNisthenumberofsteamgenerators intheplant)iftheresultsofthefirstorpreviousinspections indicatethatallsteamgenerators areperforming inalikemanner.Notethatundersomecircumstances, theoperating conditions inoneormoresteamgenerators maybefoundtobemoreseverethanthoseinothersteamgenerators.

Undersuchcircumstances thesamplesequenceshallbemodifiedtoinspectthemostsevereconditions.

2.Thethirdandfourthsteamgenerators notinspected duringthefirstinservice inspection shallbeinspected duringthesecondandthirdinspections, respectively.

Thefourthandsubsequent inspections shallfollowtheinstructions described in1above.COOKNUCLEARPLANT-UNIT13/44-13AMENDMENT NO.B&

1STSPISPECTIONTABLE4.4-2STEAMGENERATOR TUBEINSPECTIO 2NDSAMPLEINSPECTION 3RDSPLEINSPECTION SampleSizeAminimumofSTubesperS.G.ResultC-1C-2C-3ActionRequiredNonePlugorsleevedefective tubesandinspectadditional 2StubesinthisS.G.InspectalltubesinthisS.G.,plugorsleevedefective tubes,andinspect2StubesineachotherS.G.ResultN/AC-1C-2C-3AllotherS.G.sareC-1ActionRequiredN/ANonePlugorsleevedefective tubesandinspectadditional 4StubesinthisS.G.PerformactionforC-3resultoffirstsample,NoneResultN/AN/AC-1C-2C-3N/AN/AActionRequiredN/AN/ANonePlugorsleevedefective tubesPerformactionforC-3resultoffirstsampleN/AN/APromptnoti-ficationtoNRCpursuanttospecification 6.9.1SomeS.G.sC-2butnoadditional S.G.areC-3Additional S.G~isC-3PerformactionforC-2resultofsecondsampleInspectalltubesineachS.G.andplugorsleevedefective tubes.Promptnotific-ationtoNRCpursuanttospecification 6.9.1N/AN/AN/AN/An%erestenumerosteamgenerators nteunt,annstenumerosteamgenerators inspected duringaninspection COOKNUCLEARPLANT-UNIT13/44-14AMENDMENT NO.

CTCOST44CCOOLANTSYSTEMLEAKAGLGDC0SSEMSLIMITINGCONDITION FOROPERATION 3.4.6'Thefollowing ReactorCoolantSystemleakagedetection systemsshallbeOPERABLE:

a~Oneofthecontainment atmosphere particulate radioactivity monitoring channels(ERS-1301 orERS-1401),

b.Thecontainment sumplevelandflowmonitoring system,andc~Eitherthecontainment humiditymonitororoneofthecontainment atmosphere gaseousradioactivity monitoring channels(ERS-1305 orERS-1405).

APPLICBILIMODES1,2,3and4.ACTION:Withonlytwooftheaboverequiredleakagedetection systemsOPERABLE, operation maycontinueforupto30daysprovidedgrabsamplesofthecontainment atmosphere areobtainedandanalyzedatleastonceper24hourswhentherequiredgaseousand/orparticulate radioactivity monitoring channelsareinoperable; otherwise, beinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.SURVEILLANCE REUIREMENTS 4.4.6.1Theleakagedetection systemsshallbedemonstrated OPERABLEby:a~Containment atmosphere particulate andgaseous(ifbeingused)monitoring system-performance ofCHANNELCHECK,CHANNELCALIBRATION andCHANNELFUNCTIONAL TESTatthefrequencies specified inTable4.3-3,b.Containment sumplevelandflowmonitoring system-performance ofCHANNELCALIBRATION atleastonceper18months,C.Containment humiditymonitor(ifbeingused)-performance ofCHANNELCALIBRATION atleastonceper18months.COOKNUCLEARPLANT-UNIT13/44-15AMENDMENT NO.400, EACCOOSYSTEM0ERATIONAL LEAKAGELIMITINGCONDITION FOROPERATION I3.4.6.2ReactorCoolantSystemleakageshallbelimitedto:a.NoPRESSUREBOUNDARYLEAKAGE,b.1GPMUNIDENTIFIED LEAKAGE,cd600gallonsperdaytotalprimary-to-secondary leakagethroughallsteamgenerators and150gallonsperdaythroughanyonesteamgenerator, d.10GPMIDENTIFIED LEAKAGEfromtheReactorCoolantSystem,ande.52GPMCONTROLLED LEAKAGE.f.1GPMleakagefromanyreactorcoolantsystempressureisolation valvespecified inTable3.4-0~APPLICABILITY:

MODES1,2,3and4.ACTION:a.WithanyPRESSUREBOUNDARYLEAKAGE,beinatleastHOTSTANDBYwithin6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.b.WithanyReactorCoolantSystemleakagegreaterthananyoneoftheabovelimits,excluding PRESSUREBOUNDARYLEAKAGE,reducetheleakageratetowithinlimitswithin4hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.Withanyreactorcoolantsystempressureisolation valve(s)leakagegreaterthantheabovelimit,exceptwhen:1.Theleakageislessthanorequalto5.0gpm,and2.Themostrecentmeasuredleakagedoesnotexceedthepreviousmeasuredleakage*byanamountthatreducesthe*TosatisfyALARArequirements, measuredleakagemaybemeasuredindirectly (asfromtheperformance ofpressureindicators) ifaccomplished inaccordance withapprovedprocedures andsupported bycomputations showingthatthemethodiscapableofdemonstrating valvecompliance withtheleakagecriteria.

COOKNUCLEARPLANT-UNIT13/44-16AMENDMENT NO.

EACORCOOLANTSYSTEMBASES3445STEAMGENERATORS TUBEINTEGRITY TheSurveillance Requirements forinspection ofthesteamgenerator tubesensurethatthestructural integrity ofthisportionoftheRCSwillbemaintained.

Theprogramforinservice inspection ofsteamgenerator tubesisbasedonamodification ofRegulatory Guide1.83,Revision1.Inservice inspection ofsteamgenerator tubingisessential inordertomaintainsurveillance oftheconditions ofthetubesintheeventthatthereisevidenceofmechanical damageorprogressive degradation duetodesign,manufacturing errors,orinservice conditions thatleadtocorrosion.

Inservice inspection ofsteamgenerator tubingalsoprovidesameansofcharacterizing thenatureandcauseofanytubedegradation sothatcorrective measurescanbetaken.Theplantisexpectedtobeoperatedinamannersuchthatthesecond-arycoolantwillbemaintained withinthosechemistry limitsfoundtoresultinnegligible corrosion ofthesteamgenerator tubes.Ifthesecondary coolantchemistry isnotmaintained withintheseparameter limits,localized corrosion maylikelyresultinstresscorrosion cracking.

Theextentofcrackingduringplantoperation wouldbelimitedbythelimitation ofsteamgenerator tubeleakagebetweentheprimarycoolantsystemandthesecondary coolantsystem.Theallowable primary-to-secondary leakrateis150gallonsperdaypersteamgenerator.

Axialorcircumferentially orientedcrackshavingaprimary-to-secondary leakagelessthanthislimitduringoperation willhaveanadequate marginofsafetytowithstand theloadsimposedduringnormaloperation andbypostulated accidents.

Leakageinexcessofthislimitwillrequireplantshutdownandaninspection, duringwhichtheleakingtubeswillbelocatedandpluggedorrepaired.

Asteamgenerator whileundergoing creviceflushinginMode4isavailable fordecayheatremovalandisoperable/operating uponreinstatement ofauxiliary ormainfeedflowcontrolandsteamcontrol.Wastage-type defectsareunlikelywiththeallvolatiletreatment (AVT)ofsecondary coolant.However,evenifadefectofsimilartypeshoulddevelopinservice,itwillbefoundduringscheduled inservice steamgenerator tubeexaminations.

Pluggingorsleevingwillberequiredforalltubeswithimperfections exceeding therepairlimitwhichisdefinedinSpecification 4.4.5.4.a.

Steamgenerator tubeinspections ofoperating plantshavedemonstrated thecapability toreliablydetectdegradation thathaspenetrated 20%oftheoriginaltubewallthickness.

Tubesexperiencing outerdiameterstresscorrosion crackingwithinthethickness ofthetubesupportplatesarepluggedorrepairedbythecriteriaof4.4.5.4.a.10.

COOKNUCLEARPLANT-UNIT1B3/44-2aAMENDMENT NO.

REACTCOSYST~SEES3445SEAMGENERATORS TUBEINTEGRITY (Continued)

Whenevertheresultsofanysteamgenerator tubinginservice inspection fallintoCategoryC-3,theseresultswillbepromptlyreportedtotheCommission pursuanttoSpecification 6.9.1priortoresumption ofplantoperation.

Suchcaseswillbeconsidered bytheCommission onacase-by-case basisandmayresultinarequirement foranalysis, laboratory examinations, tests,additional eddy-current inspection, andrevisionoftheTechnical Specifications, ifnecessary.

COOKNUCLEARPLANT-UNIT1B3/44-2bAMENDMENT NO.

CTOCSYSBASSMaintaining anoperating leakagelimitof150gpdpersteamgenerator (600gpdtotal)willminimizethepotential foralargeleakageeventduringsteamlinebreakunderLOCAconditions.

BasedontheNDEuncertainties, bobbincoilvoltagedistribution andcrackgrowthratefromthepreviousinspection, theexpectedleakratefollowing asteamlineruptureislimitedtobelow120gpminthefaultedloopand150gpdpersteamgenerator intheintactloops,whichwilllimitoffsitedosestowithin10percentofthe10CFR100guidelines.

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.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 studiesshowthatoperation maybecontinued withcontaminant concentration levelsinexcessoftheSteadyStateLimits,uptotheTransient Limits,forthespecified limitedtimeintervals withouthavingasignificant effectonthestructural integrity oftheReactorCoolantSystem.Thetimeintervalpermitting continued operation withintherestrictions oftheTransient Limitsprovidestimefortakingcorrective actionstorestorethecontaminant concentrations towithintheSteadyStateLimits.COOKNUCLEARPLANT-UNIT1B3/44-4AMENDMENT NO.53 00Q~ESThesurveillance requirements provideadequateassurance thatconcentrations inexcessofthelimitswillbedetectedinsufficient timetotakecorrective action.3448SPECIFICACTIVITYThelimitations onthespecificactivityoftheprimarycoolantensurethattheresulting 2hourdosesatthesiteboundarywillnotexceedanappropriately smallfractionofPart100limitsfollowing asteamgenerator

-tuberuptureaccidentinconjunction withanassumedsteadystateprimary-to-secondary steamgenerator leakagerateof1.0GPM.Thevaluesforthelimitsonspecificactivityrepresent interimlimitsbaseduponaparametric evaluation bytheNRCoftypicalsitelocations.

Thesevaluesareconservative inthatspecificsiteparameters oftheCookNuclearPlantsite,suchassiteboundarylocationandmeteorological conditions, werenotconsidered inthisevaluation.

TheNRCisfinalizing sitespecificcriteriawhichwillbeusedasthebasisforthereevaluation ofthespecificactivitylimitsofthissite.Thisreevaluation mayresultinhigherlimits.Offsitedosesfollowing amainsteamlinebreakarelimitedto10percentofthe10CFR100guideline.

Thisrestriction isbasedontheresultsofaDonaldC,CookNuclearPlantsitespecificradiological evaluation thatassumesaprimarycoolantiodineactivitylevelcorresponding to1percentfueldefects(approximately 4.6microCurie/gram DOSEEQUIVALENT I-131),ratherthanaspecificactivityof1.0microCurie/gram DOSEEQUIVALENT, andapost-accident primary-to-secondary leakrateof120GPMinthefaultedloop.ReducingT>>9tolessthan500Fpreventsthereleaseofactivityshoulda0steamgenerator tuberupturesincethesaturation pressureoftheprimarycoolantisbelowtheliftpressureoftheatmospheric steamreliefvalves.Thesurveillance requirements provideadequateassurance thatexcessive'pecific activitylevelsintheprimarycoolantwillbedetectedinsufficient timetotakecorrective action.Information obtainedoniodinespikingwillbeusedtoassesstheparameters associated withspikingphenomena.

Areduction infrequency ofisotopicanalysesfollowing powerchangesmaybepermissible ifjustified bythedataobtained.

COOKNUCLEARPLANT-UNIT1B3/44-5AMENDMENT NO.

ATTACHMENT 3toAEP:NRC:1166 CURRENTPAGESMARKED-UP TOREFLECTPROPOSEDCHANGES

REACTORCOOLANTSYSTEMSHVIEILLAiCE REUIRENENTS Continued l.Alltubesthatpreviously haddetectable wallpenetrations (greaterthanorequalto20%)thathavenotbeenpluggedorrepairedbysleevingintheaffectedarea.2.Tubesinthoseareaswhereexperience hasindicated potential problems.

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

c.Thetubesselectedasthesecondandthirdsamples(ifrequiredbyTable4.4-2)duringeachinservice inspection maybesubjected toapar"ialtubeinspection provided:

1.Thetubesselectedforthesamplesincludethetubesfromthoseareasofthetubesheetarraywheretubeswithimperfections werepreviously found.~QQV2.Theinspections includethoseportionsofthetubeswheref4+A~y~iimperfeetionswerepreviously found.Theresultsofeachsampleinspection shallbeclassified intooneofthefollowing threecategories:

~CateorvInsectionResultsC-1LessthanStofthetotaltubesinspected aredegradedtubesandnoneoftheinspected tubesaredefective.

C-2Oneormoretubes,butnotmorethan1%ofthetotaltubesinspected aredefective, orbetween5%and10%ofthetotaltubesinspected aredegradedtubes.C-3Morethan10%ofthetotaltubesinspected aredegradedtubesormorethan1'0oftheinspected tubesaredefective, Note:Inallinspections, previously degradedtubesmustexhibi"significant, (greaterthanorequalto10%)furtherwallpenetrations tobeincludedintheabovepercentage calculations.

COOKNUCLEARPLANT-UNIT13/44-8AMZuDMEVr No.gg,.~~t

'I NElPii)RCggt~yySy~~gyPt~g~<~J~~~g~S

(~"n-tnuo 4.4.$.3fnsnect.on Feuencies->i.eabovereouirefinservice insyec:onsOf'%amgene.crtuoessnailbeOert'OP4td atM4tollwinqt'requenctes:

DefirStfnSarviCe inS:e.tiOn sha11bePert'O~at.e.5fffectfveFullroe.Nonthsbut~fthfn24calencaraenthso~inftfalcriticali:y.Subsequent inservfce insoectfons shallbeper.~atintervals ot'otlessthan12norcerethan24calencarnenthsaftertheprevfousinsoecfon.lf'consecu-fveinspections t'o!1o&nq serviceunderAYTcon4ftfons, notincluCfnq theOmsemicainsyec:fon, reSultin411insoec:fon resu(tsfailingint"theC-1categoryorif'cons~cfve insoectfons Ceans+"aa thatpreviously observedCegradatfon losnotcontfnueC andnoacdftfona1 d~radatfon hasoc~eC,~.einsoectfon intervalmaybeextenctt4 Uaaaxfmunot'nce)ercQmntns.C.t..ereSultSC.:heinSerV<Ce nSCeC.fOn Of4SWr~generator corcuc.ec inac-orzrce rithTab!e4.'at40nanth<ntarval5 faliin~tegoryC-3,theinspectfon t'rtquency sr'!1i"efr~.eascc"4leastoncevcr294nths.iitetnc.CaselrtihS:cotton freouenCy sral'i4py!yuntf1thesuesequent,.insoec

.OnstatfsfytheCrtteria.O.Spect...'catfon 4.4.5.3.4; thei'n:erval maythenbeextenctto4mx.mumot'nce;er 4~months.Acdftfonal, unschaCul&

inse~fceinspec.fons sna11beper.or.ecoheach5eastgenerator inaccordance efththet'irssaaplefhsec:fonspef~fecinTa'hie4.42curfagthescutumsuosecuen:

toanyot'hei'olleefnq conoftfons:

---=."""7>"--hiaaf-to.-.secondary

.Oe.leag.Jot;includfng 1eaksorfqfnatfng t'rawoe-Ca-tuoe sheet+14'i)incicadas't' the1iaftsot'pecfffcatfon 3.4.5.2.A5efsafeoc:~rance greeterthantaOyeritfng SasisEarthquake.

Alosswt'moolah accfdentctqufrfncl acestfonof'"eengfneereo sai'equals.

4,Amainsteanlineor'eedmwr1inebreak.d.Tubesleftinserviceasaresultofapplication ofthetubesupportplatealternate pluggingcriteriashallbeinspected bybobbincoilprobeduringallfuturerefueling outages.4eAaaachmnc, So REACTORCOOVQfTSvST~qSl;RVEILLA fCEREOUZREv~~iS Continued 4,4,54Acceocance Criariahsused.'nthisSpecif'cation:

Ioerfeccion meansanexception tothedimensions, finishorcontourofacubeorsleevefromthatrequiredbyfabrication dravingsorspecificacions.

Eddy-current castingindicacions belov20iofchenominalvalithickness.

ifdacectabl

~,maybeconsidered asimperfections.

2.Decradacion meansaserviceeinduced

cracking, vastage,vea.o.generalcorrosion occurring oneitherinsideoroutsideofatubeorsleeve.DexradcdTubeo.Sleevemeansanimperfection greaterthanorequalco204ofthenominalvalichickness causedbydegradacion.PercentDegradation meanscheamountofthevalithickness affectedorremovedbydegradation.

~~~l'~te!eo=teatsanLeper!sation e!authseveritythatitexoeeastherape-ii'n.it.eReai/PluinLimitmeanscheimperfection depthatorbeyondvhichthetubeorsleevedcubeshallberepairedorremovedfromservice.Anytubevhich,uponinspection, exhibitscubevalidegradation of40percentormoreofchenominalcubevalichickness shallbepluggedorrepairedpriortorecurning thesteamgeneracor toservice.anysleevevhich,uponinspection, exhibitsvalidegradation of29percentormoreofthenominalvalithickness shallbeyluggedpriorcoreturning thesceamgenerator coservice.Inaddition, anysleeveexhibiting anymeasurable valilossinsleeveexpansion transicion orveldconesshallb>>plugged.9.~tlat<<natokeispeen!stat onlyinareastherethasleeve,syanschecubesheet areaandvhoaelover]ointisat,theprimaryfluidtubesheet face.'COOKNUCLMtPLY-UNIT1~i44-10ANBCMBIT80.98.f~~t,::elBjo-'"i"ic.leaksorcontainsadefectlargeenoughcoaffectitsstructural integrity intheeventofanOperating Sasis":...,.'..-.:,.'.~.Larzhquaka; a4oaaofc'co%'am"acct'dane,'t 5'r"ia'tesi'lineorJ!aeavataz linebreakasspeoi!iea in4.a.5.3.o, shove.(r,!ptubeorsleevefroathepointofentry(hotlegaide)complecely aroundtheU-bendtothetopsupportofthecoldleg.

tNSERTAd.Implementation ofthesteamgenerator tube/tube supportplate'lternate pluggingcriteriarequiresa100%bobbinprobeinspection forhotlegtubesupportplateintersections andcoldlegintersections downtothelowestcoldlegtubesupportplatewithknownouterdiameterstresscorrosion cracking(ODSCC)indications.

Aninspection usingtherotatingpancakecoil(RPC)probeisrequiredforalltubesupportplateintersection indications forbobbincoilsignalamplitude between1.5and4.0voltsprovidedthetubeistobeleftinservice.TheRPCresultsaretobeevaluated toestablish thattheprincipal indications canbecharacterized asODSCC.Onceanindication ischaracterized asODSCC,RPCinspections willbeperformed onthisindication atalternate subsequent refueling outages.,Fortubesthatwillbeadministratively plugged,noRPCinspection isrequired.

INSERT8Thisdefinition doesnotapplyfortubesexperiencing outerdiameterstresscorrosion crackingconfirmed bybobbinprobeinspection tobewithinthethickness

-ofthetubesupportplates.See4.4.5.4.a.10 fortheplugginglimitforusewithinthethickness ofthetubesupportplate.INSERTCForatubeinwhichthetubesupportplateelevation alternate plugginglimithasbeenapplied,theinspection willincludeallthehotlegintersections andallcoldlegintersections downto,atleast,thelevelofthelastcrackindication.

'~RCOOLLYgyS~SCXRQTR~SConctnued~esteamgenerator shallbedetermined OP~LEafcetcompleteche~nCchecorresponding actions(plugging orsleevingallcubesezceedi~repairlimitandallcubescontaining through-vali cracks)tnt<<9u<edbyTabl~4.4~2.Sceaagenerator cberepairsaaybeaadainaccordance vichchemethodsdescribed ineicherVCR'12523otC&-313-P.

<.4.5.fR~'00l'llaoFolloving each'.nservica Insyeccion ofscca!jeneracor cubes,iaaf~a'r~anycub~sreguinfplugingorsleeving, thenumberofCQespluggedotsleevedineachscacajeneracot shallbereportedcoheCocaission vichin19days.~ecocyI.eroiusOfchesceasegeneracotcubeSaservice inspec'n5ha~'e'nc~udedincheequalOperating Reportperiodinvn.'cn..".'sinspection vascomylecad.

Thistepott,inc'da:fot.ieshallNuaberandextentofcubesinspected.

hLoca..'an andpercencofvali~thickness penectacioa fotind'cation ofanimperfection.

C4LeaAc~ideni.".cacion ofcubesplugedotsleeved.~Resulso.scaaagenerator cubeinsyec.'oas vhichfallintoCategoryC.3andrequireptoaycnocificacioa oftheCoaaissioa shallbereportedpursuantcoSpecificatioa 6.9.1ptiotCoreauapcion ofadeplantoperacioa.

Thevtittaafollovuyofthisreportshallovidasctiptioa ofinvescigatioas conchcted todataaiaacauseofthe5ptcubedegtadacioa andcotteccivo meaauteaca3caacoptaveattecutteace.

dTheresultsofinspections performed under4.4.5.2foralltubesinwhichthetubesupportplatealternate pluggingcriteriahasbeenappliedshallbereportedto'theCommission within15daysfollowing theinspection, Thereportshallinclude:1.Listingofapplicable tubes.2.Location(applicable intersections pertube)andextentofdegradation (voltage).

C~"~4LFmrLagt-mZTl3/44llgg,,f5' eubeSuotaeteuCisusedfordisposition ofasteamgenerator tubeforcontinued servicethatisexperiencing outerdiameterinitiated stresscorrosion crackingconfinedwithinthethickness ofthetubesupportplates.Forapplication ofthetubesupportplatealternate plugginglimit,thetube'sdisposition forcontinued servicewillbebaseduponstandardbobbinprobesignalamplitude.

Theplantspecificguidelines usedforallinspections shallbeamendedasappropriate toaccommodate theadditional information neededtoevaluatetubesupportplatesignalswithrespecttotheabovevoltage/depth parameters.

Pendingincorporation ofthevoltageverification requirement

.inASMEstandardverifications, anASMEstandardcalibrated againstthelaboratory standardwillbeutilizedintheDonaldC.CookNuclearPlantUnit1steamgenerator inspections forconsistent voltagenormalization.

l.Atubecanremaininserviceifthesignalamplitude ofacrackindication islessthanorequalto4.0volts,regardless ofthedepthoftubewallpenetration, if,asaresult,theprojected end-of-cycle distribution ofcrackindications isverifiedtoresultinprimary-to-secondary leakagelessthan120gpminthefaultedloopduringapostulated steamlinebreakevent.Themethodology forcalculating expectedleakratesfromtheprojected crackdistribution mustbeconsistent withWCAP-13187, Rev.0.2.Atubeshouldbepluggedorrepairedifthesignalamplitude ofthecrackindication isgreaterthan4.0volts.

REACTORCOOLANTSYSTEMPERATILEAKAGELIMITINGCONDITION FOROPERATION 3,4.6.2ReactorCoolantSystemleakageshallbelimitedto:a.NoPRESSUREBOUNCARYLEAKAGE,b,C.d.1GPHUNIDENTIFI~5LEAKAGE,ootoalaristary-to-secondary leakagethroughallsteamgener-atorsand%%gallons perdaythroughanyonesteamgenerator, i'/010GPMIOENTIFIEO LEAKAGEfromtheReactorCoolantSystem,ande.52GPHCONTROLLED LEAKAGE.f.1GPMleakage.'romanyreactorcoolantsystempressureisolation valvespeciried inTable3.4-0.APPLICABILITY:,%0ES

!,2,3and4ACTION:a.WithanyPRESSUREBOUNDARYLEAKAGE,beinatleastHOTSTANDBYwithin6hoursandinCOLOSHUTDOWNwithinthefollowing 30hours.b.WithanyReactorCoolantSystemleakage,reaterthananyoneoftheabovelimits,excluding PRESSUREBOUNDARYLEAKAGE,reducetheleakageratetowfthfnlimitswfthfn4hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.C.'-Withanyreactorcoolantsystempressureisolation valve(s)leak-agegreaterthantheabovelimit,exceptwhen:Theleakageislessthanorequalto5.0gpm,and2.Themostrecentmeasuredleakagedoesnotexceedthepreviousmeasuredleakage>>byanamountthatreducesthe>>osatisfyARArequirements, measuredleakagemaybemeasuredindirectly (asfromtheperformance ofpressureindicators) ifaccomplished inaccordance withapprovedprocedures andsupported bycomputations shyingthatthemethodiscapaoleofdemonstrating valvecompliance withtheleakagecriteria.

0.C.COOK-UNIT13/44-168+MgoasOJ'y4, b)REACTORCOOLAHTS'EST~USES4.45STEP&CfERAQRS~~5Ej.cfECRI'TheSuveil'.anca Requirements forinspection ofthesteamgenerator cubesensuechatC.".escrctursLi,ntsgricy ofthisportionoftheRCSviLLbemaintained.

Theprogramforinservics inspection ofsteamgenerator cubesisbasedonamodification ofReguLatory CuideL.d3,RevisionL.Inservice inspection ofsteamgereracor cubingisessential inordercomaintainsurveiLLance ofchecordic'ons ofthetub4sintheeventthatshareisevidenceofmechanical damageorprogressjvedegradation duetodesign,manufacturing errors,orinservice conditions c&tloadtocorrosion:

Inservice inspection ofsteamgenerator cubingalsoprovidesaaaansofcharacterize.ng thenatureandcauseofanycubedegradation sothatcorrective measurescanbetaken..heplantisexpected:obeoperatedinamannersuchChatthesecond.arycoolancvillbema;.".calmed vichinchosechemistry LimitsfoundCoresul.innegL'gibl

~corros'oon ofchesteamgenerator cubes.Ifthesecondary (0cooisncohscisepis..osaincsinad v'iclinchas~possessor iini'cs,locsiisod corrosion mayLikely".~suitinscresicorrosion cracking.

Thaextent,ofs'PcrackingduringPiac:oPgrecianvouidbolinseedbyCha1inieaeion atscsscgonasco.rcubaleaks~bacvsanhaprisscoaisnesscansndchasecondary

'coolanCsO'CemojCo~sedarya1ypescamgene).rsav-.p.m-o-daae1sanisimddptegiofsafddopeabsladcint.ratialahaencec'c.sedaao5alerhyrsteCor+etiaononiorsfeamorex05vireirpluoda6unedectn,1endh'steamgenerator vhileundergoing creviceflushinginHoda4isavailable fordecayheatremovalandisoperable/operac'.."g uponreinstatement ofauxiliary ormainfeedflovcontrolandscaafscontrol.Ascage-cypa defectsareunlikelyvithchaallvolatiletreatment (AVT)otsecondary coalane.Hovavar,evanitadataeeot~iniiarcypashoulddevelopinservice,icvillbatoundduringscheduled Insaryics scadsgsnoracoc cubo...'exam'.nations.

Plugg'ing orslievingvillberejuiredforalltubesvithimper~~~factionsexceeding chartpairL4%icvhichisd4fin4dinSpecificacion.....,4..4

.>.4..ua.:c,.:)~~.

)curator..

CubeAsoyecsimnS deafaParasiagn.P4ncs.

han..-demonscraced thecapability toreliablydecectdegradation chathaspenecraced 20%'ofcheoriginalt&evalithickness.

t'henever theresultsofanysceaagenerator tubinginservfce inspection fallincoCaragoryC~3,theseresultsvillbapromptlyreportedcotheCommission pursuanccoSpecification 6.9.1priorroresumption ofplantoperacion.

Suchcasesvillbeconsidered bychaCommission onacase-by.casebasisandmayresultinarequirement foranalysis, laboratory exalinacions tests.additional eddy-current inspection, andrevisionofthaTechnical Specifications, ifnecessary.

COOKmeme,sian-mIT1he%~Ho.51)pSt Theallowable primary-to-secondary leakrateisl'50gallonsperdaypersteamgenerator.

Axialorcircumferentially orientedcrackshavingaprimary-to-secondary leakagelessthanthislimitduringoperation willhaveanadequatemarginofsafetytowithstand theloadsimposedduringnormaloperation andbypostulated accidents.

Leakageinexcessofthislimitwillrequireplantshutdownandaninspection, duringwhichtheleakingtubeswillbelocatedandpluggedorrepaired.

anSA'7Fdiameterstresscorrosion crackingwithintheTubesexperiencing outerametethickness ofthetubesupportplatesarepluggedorrepaireytecrieof4.4.5.4.a.10.

Q\+R~NCMLAÃl'YST94 etostaener$t-ubeakageliofLQPHa11aalugeatornotfsatadf"etheensuretthedagec:ibutfon~tugeaka~ill."lief'toasfractionPart0Ifefn'eventfhaft.asgenerorMeptureot.aanlfbreak.lfefsc-sistan>f4'.ass4actnsusedftheansfsofesea<gadleakelfmfperstagenerator nsuresatstagenerrfsntafneinthentofanstalineureounderfons.dents.tuCAPRasSURKscu~OARYI.=-~macofanyeagnftude fsunacceptable sinceitany'efndfcatfve ofanioccndfng grossfafIureofthepressureboundary, ShouldPRESSURE8QUHOARYL=AVGF.occurthroughacoaponent vhfchcanbefsolatadfroathebalanceoftheReactorCoolantSystaa,plant,operatfon maycontinueprovfcedthe1eakfhgccgonentisprocptlyfsolatadfreyatheReactorCoolantSystaasincefsolatfon ranoves",esource.of potantfal failure.MC~TheSurvef11anca RarufranenM forRQPressurelsolatfon Valvesprovideaddedassurance ofvalveintagrity therebyreducingthepMabflfty ofgrossvalvefaflureandconsaouent fntarsystaa I.XA.Laakagef~theRCSPressureiIsolatfon ValveslstOE!fTTFi:-9 I.~QEand~f11beconsidered asaportionoftheall+red1fait.3/4.4.7CH~ISTAYThe1fafWtfons onReactorCoolantSystaacheafstry ensurethatcorrosion oftheReactorCoolantSysta!fsefnfafzed andreducesthepotantfal forReac-torCoolantSystaaleakageorfailureduetostresscorrosfon.

Hafntafnfng thecheafstry

~tthfntheSteadyStateLfafQprovfdesadequatecorrosion pro-tactfontoensurethestructural fntegrfty oftheReactorCoolantSystoleoverthe1ffaoftheplant.The4554Cfated effectsofexcaedfng theoxygen,chloride, andfluoride1faftsaretfaeandteayerature dependent.

Corrosion studfesshethatoperatfon caybecontfnuect Wthcontalfnant concantratfon levelsfnexcess-of'heShee}yStateLfafts,"uy'o:

Me7ranafent l.faith,.',orthes~ifactl,faitaatfaefnta&alswithouthavingasignificant effectonthestructural fntagrity oftheRe~tCoolantSystem.Thetfeeintervalpermitingcontinued operation

'"'v4'thorn A"mtv+fons"of'Ne.'7resfet."L+ci" provides"4foe.for" 0akQg'correc-

'tiveac:fonsCorestorethecontalfnant concantrations tovfthfn10Staacy5CataLiei&.

Thesurveillance recIugregents provideadequateassurance thatconcentrations inexcessoftheLiagtsviLLbedetectedinsufficient tiaetotakecorectiveacion.3/4.4.8SPIC'..=TC AC~.'1Z~g~L&itations onthespecicacvityofthepriaarycooLant,~nsurethattheresulting 2hourdo~esat:hesiteboundaryviLLnotexceedanappropri4teLy snaLLf:actionofPar:'.00LimitsfoLLoving asteangenera(or tube.captureacc'dentLncon]unction fait'hanaswnedsteadystatepriaag-to-secondary stecagenerator Leakagerateofl.0CPA.ThevaluesfortheL'a'=sonspeci"cactiv'-ty represent interestLiaf.tsbasedupon4paraaecrcevaluation bytheNRCofr~icalsitel,ocar.'ns

.Thesevaluesarconservacveintha5pecc5iIparaaecarsoftheCookHucLearPLantsi:e,suchassi=ebou.".da.-y locationandaeteorological conditions, verenotconsidered inzh'sevaluation.

The%Cisf'naliin'itespecificcritar'4whichviLLbeusedas.hebasisorhereevaLuation ofthespecificactivityLimitsofthissi:~,Thisraev4luat ona4yresult,inhigherLmReducingT=o'.ass".han500Fpreventsther~leaseofact'vicyshould45teachgene1oc'"e'p"e5incehesaturation pressur~ofthepriaarycooLanisbelov:..e

'.'pressureofheauospherfc stemreliefval.ves.Thesurvef,lienee reqireaentsprovideadequateassurance thatexcessive speci'cact'viyLave.'sin:h~priaarycoolantviLLbedetecadinsufcenttaetoiicecorectiveact'on.Lnforaaclon obtainedoniod.'.-.e sp'.kingviLLbesadto.assess theparameters associated 4thspikingphenoaena.

Areduction

.'nfrequency ofisotopicanalysesfoLLoving pave".changesmaybeperaissible ifJusti'edbythedataobtained.

'OCKHUCLZARPLAÃr-UNITI.g3/44-5Amendmene Ne.f/f Maintaining anoperating leakagelimitof150gpdpersteamgenerator (600gpdtotal)willminimizethepotential~

alargeleakageeventduringsteamlinebreakunderLOCAconditions.

Easedo~ntheNDEuncertainties, bobbincoilvoltagedistribution andcrackgrowthratefromthepreviousinspection, theexpectedleakratefollowing asteamlinerupture'islimitedtb1w120gpminthefaultedloopand150gpdpersteamgenerator inthete10intactloops,whichwilllimitoffsitedosestowithin10percentoftheCFR100guidelines.

Ifthepro)ected endofcycledistribution ofcrackindications resultsinprimary-to-secondary leakagegreat'erthan120gpminthefaultedloopduringapostulated steamlinebreakevent,additional tubesmustberemovedfromserviceinordertoreducethepostulated

.primary-to-secondary steamlinebreakleakagetobelow120gpm.EOffsitedosesfollowing amainsteamlinebreakarelimitedto10percentofthe10CFR100guideline.

Thisrestriction isbasedontheresultsofaDonaldC.CookNuclearPlantsitespecificradiological evaluation thatassumesaprimarycoolantiodineactivitylevelcorresponding to1percentfueldefects(approximately 4.6microCurie/gram DOSEEQUIVALENT I-131),ratherthanaspecificactivityof1,0microCurie/gram DOSEEQUIVALENT, andapost-accident primary-to<<secondary leakrateof120CPMinthefaultedloop.

ATTACHMENT 4toAEP:NRC:1166 VCAP-13187, "D.C.COOKUNIT1STEAMGENERATOR TUBEPLUGGINGCRITERIAFORINDICATIONS ATTUBESUPPORTPLATES"(PROPRIETARY)

VCAP-13188, "D.C.COOKUNIT1STEAMGENERATOR TUBEPLUGGINGCRITERIAFORINDICATIONS ATTUBESUPPORTPLATES"(NON-PROPRIETARY)

ATTACHMENT 5toAEP:NRC:1166 WESTINGHOUSE AUTHORIZATION LETTERCAV-92-282 ANDACCOMPANYING AFFIDAVIT, PROPRIETARY INFORMATION NOTICE,ANDCOPYRIGHT NOTICE

Retrieved from "https://kanterella.com/w/index.php?title=ML17329A422&oldid=737108"