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{{#Wiki_filter: | {{#Wiki_filter: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 | II4 | ||
~i3/ | ~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 | )yl1g~I | ||
.3/ | .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 | ||
~Jsw'~+S~4" | ~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. | ||
I.3/4BASES3/4.4REACTORCOOLANTSYSTEM/6/I'i3/4.4. | Thisreportshallinclude:1.NumberandextentoftubeseacLsleeces. | ||
3/4BASES3/4.4REACTORCOOLANTSYSTEMNDECOOKNUCLEARPLANT- | inspected. | ||
as's3/4BASES3/4.4REACTORCOOLANTSYSTEMl~/~v3/4.4.6REACTORCOOLANTSYSTEMLEAKAGE3/4.4.6. | 2.Locationandpercentofwall-thickness penetration foreachindication ofanimperfection. | ||
I3/ | 3.Identification oftubesplugged,~leeved-. | ||
C.Resultsofsteamgenerator tubeinspections whichfallintoCategoryC-3andrequirepromptnotification oftheCommission shallbereportedpursuanttoSpecification 6.9.1priortoresumption ofplantoperation. | |||
g~fL'Al)p4'Le 3/4BASES3/4.4REACTORCOOLANTSYSTEM3/4.4. | Thewrittenfollowupofthisreportshallprovideadescription ofinvestigations conducted todetermine causeofthetubedegradation andcorrective measurestakentopreventrecurrence. | ||
n3/4BASES--t3/4.4REACTORCOOLANTSYSTEM3/4.4.6REACTORCOOLANTSYSTEMLEAKAGE3/4.4.6. | 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$,K& | |||
c~9'81l~'kY~gpC4,."PjcIaiIl,iI"i<'IV.Kri~I%'f/''r~!4.' | c~9'81l~'kY~gpC4,."PjcIaiIl,iI"i<'IV.Kri~I%'f/''r~!4.' | ||
3/4BASES3/4.4REACTORCOOLANTSYSTEM3/4.4. | 3/4BASES3/4.4REACTORCOOLANTSYSTEM3/4.4.8SPECIFICACTIVITYThelimitations onthespecificactivityoftheprimarycoolantensurethattheresulting 2hourdosesatthesiteboundarywillnotexceedanappropriately smallfractionofPart100limitsfollowing asteamgenerator tuberuptureaccidentinconjunction withanassumedsteadystateprimary-to-secondary steamgenerator leakagerateof1.0GPM.Thevaluesforthelimitsonspecificactivityrepresent interimlimitsbaseduponaparametric evaluation bytheNRCoftypicalsitelocations. | ||
jk$a,P:<<,'l'idal;k~>q1.Q't~~'itNAll~~Al~g | 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.}} |
Revision as of 09:11, 29 June 2018
ML17326A094 | |
Person / Time | |
---|---|
Site: | Cook ![]() |
Issue date: | 08/17/1999 |
From: | AMERICAN ELECTRIC POWER CO., INC. |
To: | |
Shared Package | |
ML17326A093 | List: |
References | |
NUDOCS 9908250195 | |
Download: ML17326A094 (47) | |
Text
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$,K&
c~9'81l~'kY~gpC4,."PjcIaiIl,iI"i<'IV.Kri~I%'f/r~!4.'
3/4BASES3/4.4REACTORCOOLANTSYSTEM3/4.4.8SPECIFICACTIVITYThelimitations onthespecificactivityoftheprimarycoolantensurethattheresulting 2hourdosesatthesiteboundarywillnotexceedanappropriately smallfractionofPart100limitsfollowing asteamgenerator tuberuptureaccidentinconjunction withanassumedsteadystateprimary-to-secondary steamgenerator leakagerateof1.0GPM.Thevaluesforthelimitsonspecificactivityrepresent interimlimitsbaseduponaparametric evaluation bytheNRCoftypicalsitelocations.
Thesevaluesareconservative inthatspecificsiteparameters ofthe'CookNuclear,Plantsite,-suchassiteboundarylocationandmeteorological conditions, werenotconsidered inthisevaluation.
TheNRCisfinalizing sitespecificcriteriawhichwillbeusedasthebasisforthereevaluation ofthespecificactivitylimitsofthis'site.Thisreevaluation mayresultinhigherlimits.ReducingT,~tolessthan500'Fpreventsthereleaseofactivityshouldasteamgenerator tuberupturesincethesaturation pressureoftheprimarycoolantisbelowtheliftpressureoftheatmospheric steamreliefvalves.Thesurveillance requirements provideadequateassurance thatexcessive'specific activitylevelsintheprimlycoolantwillbedetectedinsufficient timetotakecorrective action.Information obtainedoniodinespikingwill,beusedtoassesstheparameters associated withspikingphenomena.
Areduction:in frequency ofisotopicanalyses, following powerchangesmaybepermissible ifjustified bythedataobtained.
COOKNUCLEARPLANT-UNIT IPageB3/44-5AMENDMENT 443,466,8$
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.