ML17326A094

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Proposed Tech Specs,Removing voltage-based Repair Criteria, F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarifying Bases Section
ML17326A094
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 08/17/1999
From:
AMERICAN ELECTRIC POWER CO., INC.
To:
Shared Package
ML17326A093 List:
References
NUDOCS 9908250195
Download: ML17326A094 (47)
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Attachment 4toC0799-05Page1ATTACHMENT 2TOC0799"05CURRENTPAGESMARKED-UP TOREFLECTPROPOSEDCHANGESTOUNIT1TECHNICAL SPECIFICATIONS PageNumbers3/44-73/44-83/44-93/44-103/44-113/44-lla3/44-lib3/44-123/44-14B3/44-2aB3/44-2bB3/44-2cB3/44-3B3/44-59908250i95 990817PDRADQCK0500035,5 iPPDR)

II4

~i3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMSTEAMGENERATORS LIMITINGCONDITION FOROPERATION 3.4.5Eachsteamgenerator shallbeOPERABLE.

APPLICABILITY:

MODES1,2,3a!ld4.ACTION:Withoneormoresteamgenerators inoperable, restoretheinoperable generator(s) toOPERABLEstatuspriortoincreasing Tavgabove200'F.SURVEILLANCE REUIREMENTS 4.4.5.0Eachsteamgenerator shallbedemonstrated OPERABLEbyperformance ofthefollowing augmented inservice inspection programandtherequirement ofSpecification 4.0.5.4.4.5.1SteamGenerator SamleSelection andInsection-Eachsteamgenerator shallbedetermined OPERABLEduringshutdownbyselecting andinspecting atleasttheminimumnumberofsteamgenerators specified inTable4.4-1.4.4.5.2SteamGenerator TubeSamleSelection andInsection-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.t.Thetubesselectedforeachinservice inspection shallincludeatleast3%ofthetotalnumberoftubesinallsteamgenerators; thetubesselectedfortheseinspections shallbeselectedonarandombasisexcept:Whereexperience insimilarplantswithsimilarwaterchemistry indicates criticalareastobeinspected, thenatleast50%ofthetubesinspected shallbefromthesecriticalareas.b.Thefirstsampleoftubesselectedfor,eachinservice inspection (subsequent tothepreservice inspection) ofeachsteamgenerator shallinclude:1.Alltubesthatpreviously haddetectable wallpenetrations (greaterthanorequalto20%)thathavenotbeenplugged.ThisSpecification doesnotapplyinMode4whileperforming creviceflushingaslongasLimitingConditions forOperation forSpecification 3.4.1.3aremaintained.

COOKNUCLEARPLANT-UNIT 1Page3/44-7AMENDMENT 4M,446,%0,205 03/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMSURVEILLANCE REUIREMENTS (continued)

Tubesinthoseareaswhereexperience hasindicated potential problems.

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

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

Thetubesselectedforthesamplesincludethetubesfromthoseareasofthetubesheetarraywheretubeswithimperfections werepreviously found.Theinspections includethoseportionsofthetubeswhereimperfections werepreviously found.Theresultsofeachsampleinspection shallbeclassified intooneofthefollowing threecategories:

Cat'egoOInsectionResultsC-1Lessthan5%ofthetotaltubesinspected aredegradedtubesandnoneoftheinspected tubesaredefective.

C-2Oneormoretubes,butnotmorethan1%ofthetotaltubesinspected aredefective, orbetween5%aiid10%ofthetotaltubesinspected aredegradedtubes.C-3Morethan10%ofthetotaltubesinspected aredegradedtubesormorethan1%oftheinspected tubesaredefective.

COOKNUCLEARPLANT-UNIT 1Page3/44-8AMENDMENT 48k,446,kV7,4-'78,%0,20$,215 l'EilFA' 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS

.3/4.4REACTORCOOLANTSYSTEMSURVEILLANCE REUIREMENTS (continued)

Note:Inallinspections, previously degradedtubeser-8Ieevee mustexhibitsignificant (greaterthanorequalto10%)furtherwallpenetrations tobeincludedintheabovepercentage calculations.

4.4.5.3InstionFreuencies-Theaboverequiredinservice inspections ofsteamgenerator tubesshallbeperformed atthefollowing frequencies:

OY'ap)~+net,4 o(s~~gueva4~s.Thcfirstinservice inspection shallerformedafter6Effective FullPowerMonthsutwithin24calendarmonthsofinitialcriticalit Subsequent inservicc inspections shallbeperformed atintervals ofnotlessthan12normorethan24calendarmonthsafterthepreviousinspection.

Iftwoconsecutive inspections following serviceunderAVTconditions, notincluding thepreservice inspection, resultinallinspection resultsfallingintotheC-1categoryoriftwoconsecutive inspections demonstrate thatpreviously observeddegradation hasnotcontinued andnoadditional degradation hasoccurred, theinspection intervalmaybeextendedtoamaximumofonceper40months.b.Iftheresultsofinservice inspection ofasteamgenerator conducted inaccordance withTable4.4-2at40monthintervals fallinCategoryC-3,theinspection frequency shallbeincreased toatleastonceper20months.Theincreaseininspection frequency shallapplyuntilthesubsequent inspections satisfythecriteriaofSpecification 4.4.5.3.a; theintervalmaythenbeextendedtoamaximum'of oncepcr40months.IAdditional, unscheduled inservice inspections shallbeperformed oneachsteamgenerator inaccordance withthefirstsampleinspection specified inTable4.4-2duringtheshutdown'ubsequent toanyofthefollowing conditions:

1.Primary-to-secondary tubesleaks(notincluding leaksoriginating fromtube-to-tube shcctwelds)inexcessofthelimitsofSpecification 34.6.2.2.Aseismicoccurrence greaterthantheOperating BasisEarthquake.

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

4.Amainsteamlineorfeedwater linebreak.COOKNUCLEARPLANT-UNIT 1Page3/44-9AMENDME<NT, 98,466,200,205 ilIsCt~t~g~~v4lt I3/4LIMI'HNGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMSURVEILLANCE REUIREMENTS (continued) 4.4.5.4AccetanceCriteriaAsusedinthisSpecification eI'lmerfeclion meansanexception tothedimensions, finishorcontourofatubeetaetaevtv fromthatrequiredbyfabrication diawingsorspecifications.

Eddy-current testingindications below20%ofthenominaltubewallthickness, ifdetectable, maybeconsidered asimperfections.

3.~Deradationmeansaservice-induced

cracking, wastage,wearorgeneralcorrosion occurring oneitherinsideoroutsideofatube,er-slaevs, DeradedTubeeMleevemeansanimperfection greaterthanorequalto20%ofthenominalwallthickness causedbydegradation.

5.PercentDeradationmeanstheamountofthetubewallthickness affectedorremovedbydegradation.

Pl~knsDefectmeansanimperfection ofsuchseveritythatitexceedsthe~limit.A~dt.t'oe+cu~hng gt.hda0cc-+LS6ckpe+ibd~.

PluinLimitmeanstheimperfection depthatorbeyondwhichthetube~4ceved-tubs shallbe~alret~removedfromservice.Anytubewhich,uponinspection, exhibitstubewalldegradation of40percentormoreofthcnominaltubewallthickness shallbeplugged~iaired priortoreturning thesteamgenerator toservice.Unserviceable describes thecondition ofatubeer-sleeve ifitleaksorcontainsadefectlargeenoughtoaffectitsstructural integrity intheeventofanOperating BasisEarthquake, alosswf-coolant

accident, orastcamlincorfecdwater linebrcakasspecified in4.4.5.3.c, above.~lnsectiondetermines thecondition ofthesteamgenerator tube~evefromthepointofentry(hotlegside)completely aroundtheU-bendtothetopsupportofthecoldleg.COOKNUCLEARPLANT-UNIT 1Page3/44-10AMENDMENT 98,45I;466,AVE;240,205

)yl1g~I

.3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMCOOKNUCLEARPLANT-UNIT 1Page3/44-11AMENDMENT 484,446,477,~,KO,A5,215 JIIIk 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEM/HURL(~~+)MALHURLURLLRLCOOKNUCLEARPLANT-UNIT 1Page3/44-1laAMENDMENT 215 1i~I Ih/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMSURVEILLANCE REUIREMENTS (continued) b.Thesteamgenerator shallbedetermined OPERABLEaftercompleting thecorresponding actions(plugging e~eeviagalltubesexceeding thelimitandalltubescontaining through-wall cracks)requiredbyTable4.4-2.~"Q5COOKNUCLEARPLANT-UNIT 1Page3/44-11bAMENDMENT

~208215 III\)t'I~.a4 I~/II3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMSURVEILLANCE REUIREMENTS (continued) 4.4.5.5~ReonsFollowing eachinservice inspection ofsteamgenerator tubes,'eportedtotheCommission within15days.b.Thecompleteresultsofthesteamgenerator tubeinservice inspection shallbeincludedintheAnnualOperating Reportfortheperiodinwhichthisinspection wascompleted.

Thisreportshallinclude:1.NumberandextentoftubeseacLsleeces.

inspected.

2.Locationandpercentofwall-thickness penetration foreachindication ofanimperfection.

3.Identification oftubesplugged,~leeved-.

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

Thewrittenfollowupofthisreportshallprovideadescription ofinvestigations conducted todetermine causeofthetubedegradation andcorrective measurestakentopreventrecurrence.

COOKNUCLEARPLANT-UNIT 1Page3/44-12AMENDMENT Q6,446,477,%$,%0>%$,215

~Jsw'~+S~4"4STEAMGENERATOR TUBEINSPECTITSINSPECTONNDSSEONSPECTIONSampleSi.zeResultActionRequiredResultActionRequiredResultActionRequiredAminimumofSTubesperS.G.C-1C-2C-3NonePlug~&cue.defective tubesandinspectadditional 2Stubesinthi.sS.G.InspectalltubesinthisS.G.,plug~~ua.defective tubes,andinspect2StubesineachotherS.G.N/AC-1C-2C-3AllotherS.G.sareC-1N/ANonePluga~lao~defect,ive tubesandinspectadditional 4StubesinthisS.G.PerformactionforC-3resultoffirstsampleNoneN/AN/AC-1C-2C-3N/AN/AN/ANonePlug~~ve-defective tubesPerformactionforC-3resultoffirstsampleN/AN/fPromptnoti-ficationtoNRCpursuanttospecification 6.9.1SomeS.G.sC-2butnoaddi,tional S.G.areC-3Additional S.G.isC-3PerformactionforC-2resultofsecondsampleInspectalltubesineachS.G.andplug~~lee~defective tubes.Promptnotifi.c-ationtoNRCpursuanttospecification 6.9.1N/AN/AN/AN/AMnerestenumerorsteamgenerators steamgenerators inspected duringaninspection COOKNUCLEARPLANT-UNIT13/44-14teunt,annstenumerozAMENDMENT NO.40,4541(

I.3/4BASES3/4.4REACTORCOOLANTSYSTEM/6/I'i3/4.4.5STEAMGENERATORS TUBEINTEGRITY TheSurveillance Requirements forinspection ofthesteamgenerator tubesensurethatthestructural integrity ofthisportionoftheRCSwillbemaintained.

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

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

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

ackshavingaprimary-to-secondary leakagelessthanthislimitduringoperation willhaveanadequatemarginofsafetytowithstand theloadsimposedduringnormaloperation andbypostulated accidents.

Leakageinexcessofthislimitwillrequireplantshutdownandaninspection, duringwhichtheleakingtubeswillbelocatedandpluggedw~aked.

Asteamgenerator whileundergoing creviceflushinginMode4isavailable fordecayheatremovalandisoperable/

operating uponreinstatement ofauxiliary ormainfeedflowcontrolandsteamcontrol.whichisdefinedmSpecification 4.4.5.4.a.

thecapability toreliablydetectdegradation thathaspenetrated 20%oftheoriginaltubewallthickness.

Wastage-type defectsareunlikelywiththeallvolatiletreatment (AVT)ofsecondary coolant.However,evenifadefectofsimilartypeshoulddevelopinservice,itwillbefoundduringscheduled inservice steamgenerator tubeexaminations.

Plugginger-6Ieeving; willberequiredforalltubeswithimperfections exceeding the'imitSteamgenerator tubeinspections ofoperating plantshavedemonstrated COOKNUCLEARPLANT-UNIT 1PageB3/44-2aAMENDMENT QQ,484,446,XV',ZOO,215\

3/4BASES3/4.4REACTORCOOLANTSYSTEMNDECOOKNUCLEARPLANT-UNIT IPageB3/44-2bAMENDMENT 44',2I5 I$gI 3/4BASES~3/4.4REACTORCOOLANTSYSTEM3/4.4.5STEAMGENERATORS TUBEINTEGRITY Continued Whenevertheresultsofanysteamgenerator tubinginservice inspection fallintoCategoryC-3,theseresultswillbepromptlyreportedtotheCommission pursuanttoSpecification 6.9.1priortoresumption ofplantoperation.

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

COOKNUCLEARPLANT-UNIT IPageB3/44-2cAMENDMENT Qg,~,446,%0,20$,215 I0ly~ItV'll~<'

as's3/4BASES3/4.4REACTORCOOLANTSYSTEMl~/~v3/4.4.6REACTORCOOLANTSYSTEMLEAKAGE3/4.4.6.1 LEAKAGEDETECTION SYSTEMSTheRCSleakagedetection systemsrequiredbythisspecification areprovidedtomonitoranddetectleakagefromtheReactorCoolantPressureBoundary.

Thesedetection systemsareconsistent withtherecommendations ofRegulatory Guide1.45,"ReactorCoolantPressureBoundaryLeakageDetection Systems,"

May1973.3/4.4.6.2 OPERATIONAL LEAKAGEIndustryexperience hasshownthatwhilealimitedamountofleakageisexpectedfromtheRCS,theunidentified portionofthisleakagecanbereducedtoathreshold valueoflessthan1gpm.Thisthreshold valueissufficiently lowtoensureearlydetection ofadditional leakage.The10GPMIDENTIFIED LEAKAGElimitations providesallowance foralimitedamountofleakagefromknownsourceswhosepresencewillnotinterfere withthedetection ofUNIDENTIFIED LEAKAGEbytheleakagedetection systems.Thelimitation onseallineresistance ensuresthattheseallineresistance isgreaterthanorequaltotheresistance assumedintheminimumsafeguards LOCAanalysis.

Thisanalysisassumesthatalloftheflowthatisdivertedfromiheboroninjection linetothesealinjection lineisunavailable forcorecoolintsoernieiato.Maintaining anoperating leakagelimitoii50gpdpersteamgenerator (600gpdtetwillmtntmtmtepotennforalargeleakageeventduringsteamlinebreakunderLOCAconditions.

willensurethecalculated offsitedoseswillremainwithin10percent-ofthe10CFR100requirements andthatcontrolroomhabitability continues tomeetGDC-19.Leakageintheintactloopsislimitedto150gpd.Also,the150gpdleakagelimitincorporated intothisspecification ismorerestrictive thanthestandardoperating leakagelimitandisintendedtoprovideanadditional margiHence,thereducedleakagelimit,whencombined.

withaneffective leakratemonitoring program,providesadditional assurance thatshouldasignificant leakbeexperienced inservice,itwillbedetectedandtheplantshutdowninatimelymanner.PRESSUREBOUNDARYLEAKAGEofanymagnitude isunacceptable sinceitmaybeindicative ofanimpending grossfailureofthepressureboundary.

ShouldPRESSUREBOUNDARYLEAKAGEoccurthroughacomponent whichcanbeisolatedfromthebalanceoftheReactorCoolantSystem,plantoperation maycontinueprovidedtheleakingcomponent ispromptlyisolatedfromtheReactorCoolantSystemsinceisolation removesthesourceofpotential failure.COOKNUCLEARPLANT-UNIT IPageB3/44-3AMENDMENT

$3,N,454.,~,%0,215 I'h0IlleIM IIIklh3/4BASES3/4.4REACTORCOOLANTSYSTEMI4/JV3/4.4.8SPECIFICACTIVITYThelimitations onthespecificactivityoftheprimarycoolantensurethattheresulting 2hourdosesatthesiteboundarywillnotexceedanappropriately smallfractionofPart100limitsfollowing asteamgenerator tuberuptureaccidentinconjunction withanassumedsteadystateprimaiy-to-secondary steamgenerator leakagerateof1.0GPM.Thevaluesforthelimitsonspecificactivityrepresent interimlimitsbaseduponaparametric evaluation bytheNRCoftypicalsitelocations.

Thesevaluesareconservative inthatspecificsiteparameters oftheCookNuclearPlantsite,suchassiteboundarylocationandmeteorological conditions, werenotconsidered inthisevaluation.

TheNRCisfinalizing sitespecificcriteriawhichwillbeusedasthebasisforthereevaluation ofthespecificactivitylimitsofthissite.Thisreevaluation mayresultinhigherlimits.ReducingT,~tolessthan500'Fpreventsthereleaseofactivityshouldasteamgenerator tuberupturesincethesaturation pressureoftheprimarycoolantisbelowtheliftpressureoftheatmospheric steamreliefvalves.Thesurveillance requirements provideadequateassurance thatexcessive specificactivitylevelsintheprimarycoolantwillbedetectedinsufficient timetotakecorrective action.Information obtainedoniodinespikingwillbeusedtoassesstheparameters associated withspikingphenomena.

Areduction infrequency ofisotopicanalysesfollowing powerchangesmaybepermissible ifjustified bythedataobtained.

COOKNUCLEARPLANT-UNIT IPageB3/44-5AMENDMENT 445,466,200 Attachment 4toC0799-05Page1ATTACHMENT 3TOC0799-05PROPOSEDCHANGESTOUNIT1TECHNICAL SPECIFICATIONS PageNumbers3/44-73/44-83/44-93/44-103/44-113/44-123/44-14B3/44-2aB3/44-3B3/44-5 1lII I3/4LIMH'INGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS

~3/4.4REACTORCOOLANTSYSTE<MSTEAMGENERATORS LIMITINGCONDITION FOROPERATION 3.4.5Eachsteamgenerator shallbeOPERABLE.

APPLICABILITY:

MODES1,2,3and4.ACTION:Withoneormorestcamgenerators inoperable, restoretheinoperable generator(s) toOPERABLEstatuspriortoincreasing T,~above200'F.SURVEILLANCE REUIREMENTS 4.4.5.0Eachsteamgenerator shallbedemonstrated OPERABLEbyperformance ofthefollowing augmented inservice inspection programandtherequirement ofSpecification 4.0.5.4.4.5.1SteamGenerator SamleSelection andInstion-Eachsteamgenerator shallbedetermined OPERABLEduringshutdownbyselecting andinspecting atleasttheminimumnumberofsteamgenerators specified inTable4.4-1.4.4.5.2SteamGenerator TubeSamleSelection andInsction-Thesteamgenerator tubeminimumsamplesize,inspection resultclassification, andthecorresponding actionrequiredshallbeasspecified in.Table4.4-2.Theinservice inspection ofsteamgenerator tubesshallbeperformed atthefrequencies specified inSpecification 4.4.5.3andtheinspected tubesshallbeverifiedacceptable pertheacceptance criteriaofSpecification 4.4.5.4.ThetubesselectedforeachIinservice inspection shallincludeatleast3%ofthetotalnumberoftubesinallsteamgenerators; thetubesselectedfortheseinspections shallbeselectedonarandombasisexcept:Whereexperience insimilarplantswithsimilarwaterchemistry indicates criticalareastobeinspected, thenatleast50%ofthetubesinspected shallbcfromthesecriticalareas.b.Thefirstsampleoftubesselectedforeachinservice inspection (subsequent tothepreservice inspection) ofeachsteamgenerator shallinclude:1.Alltubesthatpreviously haddetectable wallpenetrations (greaterthanorequalto20%)thathavenotbeenplugged..

ThisSpecification doesnotapplyinMode4whileperforming creviceflushingaslongasLimitingConditions forOperation forSpecification 3.4.1.3aremaintained.

COOK'NUCLEAR PLANT-UNIT 1Page3/44-7AMENDMENT 403,466,$$,%5 lflIihe>>lk<l>4"la't~~4II'~I4,4lJlJ CI~3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS

>3/4.4REACTORCOOLANTSYSTEMSURVEILLANCE REUIREMENTS (continued) 2.Tubesinthoseareaswhereexperience hasindicated potential problems.

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

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

1.Thetubesselectedforthesamplesincludethetubesfromthoseareasofthetubesheetarraywheretubeswithimperfections werepreviously found.2.Theinspections includethoseportionsofthetubeswhere,imperfections werepreviously found.Theresultsofeachsampleinspection shallbeclassified intooneofthefollowing threecategories:

CategoOInsctionResultsC-1Lessthan5%ofthetotaltubesinspected aredegradedtubesandnoneoftheinspected tubesaredefective.

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

COOKNUCLEARPLANT-UNIT IPage3/44-8AMENDMENT S,466,%VV,4V8, 1~It/11a11I1N~1tIIg(IA~1'l~4~1~,1~>111<I11)~lcttI>>

I3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS

.i3/4.4REACTORCOOLANTSYSTEMSURVEILLANCE REUIREMENTS (continued)

Note:Inallinspections, previously degradedtubesmustexhibitsignificant (greaterthanorequalto10%)furtherwallpenetrations tobeincludedintheabovepercentage calculations.

4.4.5.3InsctionFreuencies-Theaboverequiredinservice inspections ofsteamgenerator tubesshallbeperformed atthefollowing frequencies:

b.Thefirstinservice inspection shallbeperformed after6Effective FullPowerMonthsbutwithin24calendarmonthsofinitialcriticality orreplacement ofsteamgenerators.

Subsequent inservice inspections shallbeperformed atintervals ofnotlessthan12normorethan24calendarmonthsafterthepreviousinspection.

Iftwoconsecutive inspections following serviceunderAVTconditions, notincluding thepreservice inspection, resultinallinspection resultsfallingintotheC-1categoryoriftwoconsecutive inspections demonstrate thatpreviously observeddegradation hasnotcontinued andnoadditional degradation hasoccurred, theinspection intervalmaybeextendedtoamaximumofonceper40months.Iftheresultsofinservice inspection ofasteamgenerator conducted inaccordance withTable4.4-2at40monthintervals fallinCategoryC-3,theinspection frequency shallbeincreased toatleastonceper20months.Theincreaseininspection frequency shallapplyuntilthesubsequent inspections satisfythecriteriaofSpecification 4.4.5.3.a; theintervalmaythenbeextendedtoamaximumofonceper40months.C.Additional, unscheduled inservice inspections shallbeperformed oneachsteamgenerator inaccordance withthefirstsampleinspection specified inTable4.4-2duringtheshutdownsubsequent toanyofthefollowing conditions:

Primary-to-secondary tubesleaks(notincluding leaksoriginating fromtube-to-tube sheetwelds)inexcessofthelimitsofSpecification 3.4.6.2.Aseismicoccurrence greaterthantheOperating BasisEarthquake.

Alosswf~lant accidentrequiring actuation oftheengineered safeguards.

Amainsteamlineorfeedwater linebreak.COOKNUCLEARPLANT-UNIT IPage3/44-9AMENDMENT 98,466,200i285 III~gNl'Cgt'hel,~I~44~0~8N s3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMSURVEILLANCE REUIREMENTS (continued) 4.4.5.4AccetanceCriteriaaeAsusedinthisSpecification:

~lmrfectionmeansanexception tothedimensions, finishorcontourofatubefromthatrequiredbyfabrication drawingsorspecifications.

Eddy-current testingindications below20%ofthenominaltubewallthickness, ifdetectable, maybeconsidered asimperfections.

~Deradationmasmaservice-induced

cracking, wastage,wearorgeneralcorrosion occurring oneitherinsideoroutsideofatube.Ithickness causedbydegradation.

4.PercentDeradationmeanstheamountofthetubewallthickness affectedorremovedbydegradation.

g.Defectmeansanimperfection ofsuchseveritythatitexceedstheplugginglimit.Atubecontaining adefectisdefective.

removedfromservice.Anytubewhich,uponinspection, exhibitstubewalldegradation of40percentormoreofthenominaltubewallthickness shallbepluggedpriortoreturning thesteamgenerator toservice.Unserviceable describes thecondition ofatubeifitleaksorcontainsadefectlargeenoughitoaffectitsstructural integrity intheeventofanOperating BasisEarthquake, aloss-of-coolantaccident, orasteamlineorfeedwater linebreakasspecified in4.4.5.3.c, above.~tnsctiondetermines thecondition ofthesteamgenerator tubefromthepointofentry(hotlegside)completely aroundtheU-bendtothetopsupportofthecoldleg.COOKNUCLEARPLANT-UNIT 1Page3/44-10AMENDMENT 98,45k,466k 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS o3/4.4REACTORCOOLANTSYSTEMb.Thesteamgenerator shallbedetermined OPERABLEaftercompleting thecorresponding actions(plugging alltubesexceeding theplugginglimitandalltubescontaining through-wall cracks)requiredbyTable4.4-2.COOKNUCLEARPLANT-UNlT 1Page3/44-11AMENDMENT 45k)466)%VV)4V8)200)205)K5 I1gi11pp g3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS

>3/4.4REACTORCOOLANTSYSTEMSURVEILLANCE REUIREMENTS (continued) 4.4.5.5~ReortsFollowing eachinservice inspection ofsteamgenerator tubes,thenumberoftubespluggedineachsteamgenerator shallbereportedtotheCommission within15days.Thecompleteresultsofthesteamgenerator tubeinservice inspection shallbeincludedintheAnnualOperating Reportfortheperio'dinwhichthisinspection wascompleted.

Thisreportshallinclude:1.Numberandextentoftubesinspected.

2.Locationandpercentofwall-thickness penetration foreachindication ofanimperfection.

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

Thewrittenfollowupofthisreportshallprovideadescription ofinvestigations conducted todetermine, causeofthetubedegradation andcorrective measurestakentopreventrecurrence.

COOKNUCLEARPLANT-UNIT 1Page3/44-12AMENDMENT 483,466,%VV,4V8, gV8~i(Whlw'%>~ll1,~<rSOIVk~

0OISTSAMPLEINSPECHON TABLE4.4-2SrEAMGENERATOR TUBEINSPECrlON 2NDSAMPLEINSPECTION 3RDSAMPLEINSPECTION SampleSizeAminimumofSTubesperS.G.ResultC-1C-2ActionRequiredNonePlugdefective tubesandinspectadditional 2StubesinthisS.G.ResultN/AC-1C-2ActionRequiredN/ANonePlugdefective tubesandinspectadditional 4StubesinthisS.G.ResultN/AN/AC-1NoneActionRequiredN/AN/AC-3InspectalltubesinthisS.G.,plugdefective tubes,andinspect2StubesineachotherS.G.C-3AllotherS.G.sareC-1PerformactionforC-3resultoffirstsampleNoneC-2C-3N/AN/APlugdefective tubesPerformactionforC-3resultoffirstsampleN/AN/APromptnotification toNRCpursuanttospecification 6.9.1SomeS.G.sC-2butnoadditional S.G.sareC-3Additional S.G.isC-3PerformactionforC-2resultofsecondsampleInspectalltubesineachS.G.andplugdefective tubes.Promptnotification toNRCpursuanttospecification 6.9.1N/AN/AN/AN/AS=3(N/n)%Nisthenumberofsteamgenerators intheunit,andnisthenumberofsteamgenerators inspected duringaninspection.

g~fL'Al)p4'Le 3/4BASES3/4.4REACTORCOOLANTSYSTEM3/4.4.5STEAMGENERATORS 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.Theplantisexpectedtobeoperatedinamannersuchthatthesecondary coolantwillbemaintained withinthosechemistry limitsfoundtoresultinnegligible corrosion ofthesteamgenerator tubes.Ifthesecondary coolantchemistry isnotmaintained withintheseparameter limits,localized corrosion maylikelyresultinstresscorrosion cracking.

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

Crackshavingaprimary-to-secondary leakagelessthanthislimitduringoperation willhaveanadequatemarginofsafetytowithstand theloadsimposedduringnormaloperation andbypostulated accidents.

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

Pluggingwillberequiredforalltubeswithimperfections exceeding theplugginglimitwhichisdefinedinSpecification 4.4.5.4.a.6.

Steamgenerator tubeinspections ofoperating plantshavedemonstrated thecapability toreliablydetectdegradation thathaspenetrated 20%oftheoriginaltubewallthickness.

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

Suchcaseswillbeconsidered bytheCommission onacase-blase basisandmayresultinarequirement foranalysis, laboratory examinations, tests,additional eddywurrent inspection, andrevisionoftheTechnical Specifications, ifnecessary.

COOKNUCLEARPLANT-UNIT 1PageB3/44-2aAMENDMENT 403,45k,466 I~hl)T'VC"IIWe~lg4<<

n3/4BASES--t3/4.4REACTORCOOLANTSYSTEM3/4.4.6REACTORCOOLANTSYSTEMLEAKAGE3/4.4.6.1 LEAKAGEDETECTION SYSTEMSTheRCSleakagedetection systemsrequiredbythisspecification areprovidedtomonitoranddetectleakagefromtheReactorCoolantPressureBoundary.

Thesedetection systemsareconsistent withtherecommendations ofRegulatory Guide1.45,"ReactorCoolantPressureBoundaryLeakageDetection Systems,"

May1973.3/4.4.6.2 OPERATIONAL LEAKAGEIndustryexperience hasshownthatwhilealimitedamountofleakageisexpectedfromtheRCS,theunidentified portionofthisleakagecanbereducedtoathreshold valueoflessthan1gpm.Thisthreshold valueissufficiently lowtoensureearly-detection ofadditional leakage.The10GPMIDENTIFIED LEAKAGElimitations provides:allowance foralimitedamount'of leakagefromknownsourceswhosepresencewillnotinterfere withthedetection ofUNIDENTIFIED LEAKAGEbytheleakagedetection systems.Thelimitation onseallineresistance ensuresthattheseallineresistance isgreaterthanorequalto.theresistance assumedintheminimumsafeguards LOCAanalysis.

Thisanalysisassumesthatalloftheflowthatisdivertedfromtheboroninjection linetothesealinjection lineisunavailable forcorecooling.'Maintaining anoperating leakagelimitof150gpd.persteamgenerator (600gpdtotal)willminimizethepotential foralargeleakageeventduringsteamlinebreakunderLOCAconditions.

Thisoperating leakagelimitwillensurethecalculated offsitedoseswillremainwithin10percentofthe10CFR100requirements andthatcontrolroomhabitability continues tomeetGDC-19.Leakageintheintactloopsislimitedto150gpd.Also,the150gpdleakagelimitincorporated intothisspecification ismorerestrictive thanthestandardoperating leakagelimitandisintendedtoprovideanadditional margin.Hence,thereducedleakagelimit,.when combinedwithaneffective leakratemonitoring program,providesadditional assurance thatshouldasignificant leakbeexperienced inservice,itwillbedetectedandtheplantshutdowninatimelymanner.PRESSUREBOUNDARYLEAKAGEofanymagnitude isunacceptable sinceitmaybeindicative ofanimpending grossfailureofthepressureboundary.

ShouldPRESSUREBOUNDARYLEAKAGEoccurthroughacomponent whichcanbeisolatedfromthebalanceoftheReactorCoolantSystem,plantoperation maycontinueprovidedtheleakingcomponent ispromptlyisolatedfromtheReactorCoolantSystemsince.isolation.

removesthesourceofpotential failure.COOKNUCLEARPLANT-UNIT IPageB3/44-3AMENDMENT 53,63,45%,463,8$,K&

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3/4BASES3/4.4REACTORCOOLANTSYSTEM3/4.4.8SPECIFICACTIVITYThelimitations onthespecificactivityoftheprimarycoolantensurethattheresulting 2hourdosesatthesiteboundarywillnotexceedanappropriately smallfractionofPart100limitsfollowing asteamgenerator tuberuptureaccidentinconjunction withanassumedsteadystateprimary-to-secondary steamgenerator leakagerateof1.0GPM.Thevaluesforthelimitsonspecificactivityrepresent interimlimitsbaseduponaparametric evaluation bytheNRCoftypicalsitelocations.

Thesevaluesareconservative inthatspecificsiteparameters ofthe'CookNuclear,Plantsite,-suchassiteboundarylocationandmeteorological conditions, werenotconsidered inthisevaluation.

TheNRCisfinalizing sitespecificcriteriawhichwillbeusedasthebasisforthereevaluation ofthespecificactivitylimitsofthis'site.Thisreevaluation mayresultinhigherlimits.ReducingT,~tolessthan500'Fpreventsthereleaseofactivityshouldasteamgenerator tuberupturesincethesaturation pressureoftheprimarycoolantisbelowtheliftpressureoftheatmospheric steamreliefvalves.Thesurveillance requirements provideadequateassurance thatexcessive'specific activitylevelsintheprimlycoolantwillbedetectedinsufficient timetotakecorrective action.Information obtainedoniodinespikingwill,beusedtoassesstheparameters associated withspikingphenomena.

Areduction:in frequency ofisotopicanalyses, following powerchangesmaybepermissible ifjustified bythedataobtained.

COOKNUCLEARPLANT-UNIT IPageB3/44-5AMENDMENT 443,466,8$

jk$a,P:<<,'l'idal;k~>q1.Q't~~'itNAll~~

Al~g Attachment 4toC0799-05Page1ATTACHMENT 4TOC0799-05ENVIRONMENTAL ASSESSMENT TheLicenseehasevaluated thislicenseamendment requestagainstthecriteriaforidentification oflicensing andregulatory actionsrequiring environmental assessment inaccordance with10CFR51.21.TheLicenseehasdetermined thatthislicenseamendment requestmeetsthecriteriaforacategorical exclusion setforthin10CFR51.22(c)(9).Thischangeisbeingproposedasanamendment toalicenseissuedpursuantto10CFR50thatchangesarequirement withrespecttoinstallation oruseofafacilitycomponent locatedwithintherestricted area,asdefinedin10CFR20,orthatchangesaninspection orasurveillance requirement, andtheamendment meetsthefollowingspecificcriteria.

(i)Theamendment involvesnosignificant hazardsconsideration.

Asdemonstrated inattachment 1,thisproposedamendment doesnotinvolveanysignificant hazardsconsideration.

(ii)Thereisnosignificant changeinthetypesorsignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite.Asdocumented inattachment 1,therewillbenosignificant changeinthetypesorsignificant increaseintheamountsofanyeffluents releasedoffsite.(iii)Thereisnosignificant increaseinindividual orcumulative occupational radiation exposure.

Therewillbenochangeinthelevelofcontrolsormethodology usedforprocessing ofradioactive effluents orhandlingofsolidradioactive waste,noristheproposalanticipated toresultinanychangeinthenormalradiation levelswithintheplant.Therefore, therewillbenoincreaseinindividual orcumulative occupational radiation exposureresulting fromthischange.

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