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| {{#Wiki_filter:ATTACHMENT 4TOAEP:NRC:1071N EXISTINGTECHNICAL SPECIFICATIONS PAGESMARKED-UP TOREFLECTPROPOSEDCHANGESDONALDC.COOKNUCLEARPLANTUNITS1AND29'102250233 PDRADOCKK05000315PDR lpltvW bEt'al.~npic5[467,~CgSIdC~b~~s,~iecee&dkisiecd kretnecScg'~ceiigancnra4vnce jp3.CS~0-ASSecacecnriedeneeevb'~ | | {{#Wiki_filter:ATTACHMENT 4 TO AEP:NRC:1071N EXISTING TECHNICAL SPECIFICATIONS PAGES MARKED-UP TO REFLECT PROPOSED CHANGES DONALD C.COOK NUCLEAR PLANT UNITS 1 AND 2 9'102250233 PDR ADOCK K 05000315 PDR lpl t vW b Et'al.~n pic 5[467,~C g S I dC~b~~s,~iec ee&dkisiecd kr etnecSc g'~c eii g an cnra4vnce jp 3.CS~0-ASS ec ace cnriedeneeevb'~ |
| d4eveSR'.,uc'cPhbcen&
| | d4eve SR'.,uc'cPhbcen& |
| o-shekk>s]ssoKW5/~]and,BX)(oh/PiOF~ | | o-she kk>s]sso KW5/~]and, BX)(oh/PiOF~ |
| +t~~on~PW3P~~~s'~~t7xlTcL~Llyoc.4ZSo'~~~<<-S>>%raiSniSc~u~.b.CeZaaccordance viththecoderequirements specified inSection4.1.Cyithallovance fornormaldegradation pursuanttoth>>applicable | | +t~~on~PW3 P~~~s'~~t7xlT cL~Lly oc.4 ZSo'~~~<<-S>>%ra iSniS c~u~.b.Ce Za accordance vith the code requirements specified in Section 4.1.C yith allovance for normal degradation pursuant to th>>applicable |
| $~eillance Requirements, Forapressureof2485psig00Poratemperature of6SOP,excepttorthepreaaurixer vhichiaC40PeVOLDHE5.4'5.5Thetotalcontained volumeofthoroacto$coolantsystemia12,612+100cubicfeetatanominalTof70P.avgEMERCENCY CORECOOLIVQSYSTEMS5.5.1*Theemergency corecoolingsystemsaredesignedandshallbomaintained inaccordance viththeoriginaldesignprovisiona contained inSection6.2ofthepSARvithallovance fornormaldegradation pursuanttothoappl,icable Surveillance Requirements. | | $~eillance Requirements, For a pressure of 2485 psig 0 0 Por a temperature of 6SO P, except tor the preaaurixer vhich ia C40 Pe VOLDHE 5.4'5.5 The total contained volume of tho roacto$coolant system ia 12, 612+100 cubic feet at a nominal T of 70 P.avg EMERCENCY CORE COOLIVQ SYSTEMS 5.5.1*The emergency core cooling systems are designed and shall bo maintained in accordance vith the original design provisiona contained in Section 6.2 of the pSAR vith allovance for normal degradation pursuant to tho appl,icable Surveillance Requirements. |
| 5.6FUELSTORAGECRITICALITY | | 5.6 FUEL STORAGE CRITICALITY |
| -'PENTFUELe5.6.1.1:Thespentfuelstorageracksaredesignedandshallbemaintained vith:a.Ak<<eqivalentto1.assthan0:5vhenfloodedvithunborated vater,b~Anominal10,5inchcenter-to-cen:er distancebetveenfuelassemblies placedinthestorageracks.4%/4FR7Rc.1.hseparateregionvithinthespentfuelstorageracks(definedasRegion1.)shallbeestablished | | -'PENT FUEL e 5.6.1.1: The spent fuel storage racks are designed and shall be maintained vith: a.A k<<eq ivalent to 1.ass than 0:5 vhen flooded vith unborated vater, b~A nominal 10,5 inch center-to-cen:er distance betveen fuel assemblies placed in the storage racks.4%/4FR7 R c.1.h separate region vithin the spent fuel storage racks (defined as Region 1.)shall be established |
| =orstorageofWestinghouse | | =or storage of Westinghouse |
| :ue4~MSGR6CVlTheboundezybeeveentheRedionSl".eneioned ebovetee~HL)shallbesuchthattheshallbecarriedintoRegioinFigurc5.6-1.storagerequirement 2by,atleast,onerovasshovn~~AT'Pt:QtscofccneL~caks | | :ue 4~MSGR 6 CVl The boundezy beeveen the RedionSl".eneioned ebove tee~HL)shall be such that the shall be carried into Regio in Figurc 5.6-1.storage requirement 2 by, at least, one rov as shovn~~AT'Pt: Qt s cof ccneL~caks |
| ~~S.qavi~occcQV-ZSS~~g,cdd4ien5;SSogw3/blTO~ | | ~~S.qa vi~occcQ V-ZSS~~g,cdd 4ien 5;SSo gw3/blTO~Con[i~a8ccnat'.~~ |
| Con[i~a8ccnat'.~~ | | i~~~S.+dL cd's<~~COOK NUCLEAR PLANT-UNIT 1 5-5 AMENDMENT NO R~bb.eo.6 I WlesL~o~~4~~g~<Q~+ony~gchlcH~~~5.6 tg l.p,L f I~r t'lA I I I I I I I aegaeon 2 I I I I I I ME+pleuaE Ernpvg Ce~'c" a s V~~-"'<"-ea=:'.a."."=='.".e.-..a"==="": e3.S.c."ace Racks~we.".caen" No. |
| i~~~S.+dLcd's<~~COOKNUCLEARPLANT-UNIT15-5AMENDMENT NOR~bb.eo.6IWlesL~o~~4~~g~<Q~+ony~gchlcH~~~5.6 tgl.p,LfI~rt'lA IIIIIIIaegaeon2IIIIIIME+pleuaEErnpvgCe~'c"asV~~-"'<"-ea=:'.a."." | | *I~M+)C~C Z l 0 o~'DESI'XLTTHtXS tuel atored in the spent fuel storage racks shall have~max~aCe&al fuel assembly enrichment aa follon: a 4 t Hasid%Nominal tuel Aaaeably Enrichment 4 235 1)Veatinghouse 15 x 15 STD 15 x 15 OFA 2)Exxon/AHF-15 x 15 4.95 3.50 3)Vestinghouse 17 x 17 STD 17 x 17 OFA 17 x 17 VS 4,95 4)Exxon/ANF 17 x 17 4,23 CRITICALITY-NEV FUEL 5.6.2.1 The ncv fuel pit storage racks are designed and shall be maintained vt.th a nominal 21 inch ccntcr-to-center distance betveen nev fuel assemblies such that k f vill not exceed 0.98 vhcn fuel asscmbli.es are placed in the pit cff and aqueous oam moderation i.s assu.ed.5.6.2.2 Fuel stored'n the ncv f cl storage ra=..s shall have a maximum nominal fuel assembly enrich.=cnt as follovs;Naximum No=.nal Fuel Assembly Enrichment Vt.\235 1)Vcstinghousc 1.5 x 15 STD 15 x 15 OFA 4.55 2)Exxon/ANF 15 x 15 3.50 3)Vcsti.nghouse 17 x 1.7 STD 17 x 17 OFA 17 x 17 VS 4.55 4)Exxon/ANF 17 x 17 4.23 DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent drai.ni.ng of thc pool belov elevation 629'4".COOK NUCLEAR PLANT-UNIT 1 AMENDMENT NO.6 |
| =='.".e.-..a" | |
| ==="":e3.S.c."aceRacks~we.".caen" No. | |
| *I~M+)C~CZl0 o~'DESI'XLTTHtXS tuelatoredinthespentfuelstorageracksshallhave~max~aCe&alfuelassemblyenrichment aafollon:a4tHasid%NominaltuelAaaeablyEnrichment 42351)Veatinghouse 15x15STD15x15OFA2)Exxon/AHF | |
| -15x154.953.503)Vestinghouse 17x17STD17x17OFA17x17VS4,954)Exxon/ANF 17x174,23CRITICALITY-NEVFUEL5.6.2.1Thencvfuelpitstorageracksaredesignedandshallbemaintained vt.thanominal21inchccntcr-to-center distancebetveennevfuelassemblies suchthatkfvillnotexceed0.98vhcnfuelasscmbli.es areplacedinthepitcffandaqueousoammoderation i.sassu.ed.5.6.2.2Fuelstored'nthencvfclstoragera=..sshallhaveamaximumnominalfuelassemblyenrich.=cnt asfollovs;NaximumNo=.nalFuelAssemblyEnrichment Vt.\2351)Vcstinghousc 1.5x15STD15x15OFA4.552)Exxon/ANF 15x153.503)Vcsti.nghouse 17x1.7STD17x17OFA17x17VS4.554)Exxon/ANF 17x174.23DRAINAGE5.6.3Thespentfuelstoragepoolisdesignedandshallbemaintained topreventinadvertent drai.ni.ng ofthcpoolbelovelevation 629'4".COOKNUCLEARPLANT-UNIT1AMENDMENT NO.6 | |
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| ~iLMSZaaTrk~kEI~kCITffC4aN't1storage!1isdisigedandshilbemitaiedvithastoragecapcityi~tedtonomorethn2050fuelassemblies. | | ~i L MSZaa Trk~kEI~kCITf f C 4 aN't 1 storage!1 is disig ed and sh il be mi tai ed vith a storage cap city i~ted to no more th n 2050 fuel assemblies. |
| 57SEISMICC~SIPIChTIOH 57,]noaestructuree, systemsandcomponents inthePS'hallbedesignedandmaintained tocontained intheTSARvithellovance fornormalapplicant Surreillance Requirements, identified aaCategoryIItemsoriginaldesignprovisions degradation pursuanttothe5.INETEOROLOC ICALTOVERLOChTION5.8.1Themeteorological tovershallbelocatedasshovninFigure5.1-1.5.9COMPONENT CYCLICORTRANSIENT LIMIT+Pl5,9.1Thecomponents identified inTable5.9-1aredesignedandshallbe.maintained vithinthecyclicortransient limitsofTable5.9-1.VCOOKNUCLEhRPEDANT-UNITh.'KNDNENT NO.1 41~
| | 5 7 SEISMIC C~SIPIChTIOH 5 7,]noae structuree, systems and components in the PS'hall be designed and maintained to contained in the TSAR vith ellovance for normal applicant Surreillance Requirements, identified aa Category I Items original design provisions degradation pursuant to the 5.I NETEOROLOC ICAL TOVER LOChTION 5.8.1 The meteorological tover shall be located as shovn in Figure 5.1-1.5.9 COMPONENT CYCLIC OR TRANSIENT LIMIT+Pl 5,9.1 The components identified in Table 5.9-1 are designed and shall be.maintained vithin the cyclic or transient limits of Table 5.9-1.V COOK NUCLEhR PEDANT-UNIT h.'KNDNENT NO.1 4 1~ |
| TADLE5.9-1COHPONENT CYCLICORTRANSIENT LIHITSCOHPONENT ReactorCoolantSysteaCYCLICORTRANSIENT LIHIT200heatupcyclesat<100'F/hrand200cooldowncyclesat<100F/hr(pressurizer cooldownat<200F/hr).80lossofloadcycles.40cyclesoflossofoffsiteA.C.electrical power.SOcyclesoflossofflowinonereactorcoolantloop.400reactortripcycles.200largestepdecreases inload.DESIlaNCYCLEORTRANSIENT lleatupcycle-Tfrota<200'Fhr>.F.Cooldowncycle-Tfroe>5i7'Fto<200'FHlthoutiasediate turbineorreactortrip.LossofoffsiteA.C.electrical powersourcesupplying theonslteClasslEdistribution systea.Lossofonlyonereactorcoolantpump.lOOXtoOCofRATEOTIIEHHALPNER.100Kto5XofRATEOTllERHALPOHERwithsteaaduep.
| | TADLE 5.9-1 COHPONENT CYCLIC OR TRANSIENT LIHITS COHPONENT Reactor Coolant Systea CYCLIC OR TRANSIENT L IHIT 200 heatup cycles at<100'F/hr and 200 cooldown cycles at<100 F/hr (pressurizer cooldown at<200 F/hr).80 loss of load cycles.40 cycles of loss of offsite A.C.electrical power.SO cycles of loss of flow in one reactor coolant loop.400 reactor trip cycles.200 large step decreases in load.DES IlaN CYCLE OR TRANSIENT lleatup cycle-T frota<200'F hr>.F.Cooldown cycle-Tfroe>5i7'F to<200'F Hl thout iasediate turbine or reactor trip.Loss of offsite A.C.electrical power source supplying the onslte Class lE distribution systea.Loss of only one reactor coolant pump.lOOX to OC of RATEO TIIEHHAL PNER.100K to 5X of RATEO TllERHAL POHER with steaa duep. |
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| TABLE5.9-1LQHPONENT CYCLICORTRANSIENT LIMITSCOHPONENT I(eactorCoolantSystemCYCLICORTRANSIENT LIHITla@inreactorcoolantpipebreak.Operating UasisEartlviuakes 50leaktests.5hydrostatic pressuretestsDESIGNCYCLEORTRANSIENT Ureakinareactorcoolantpipe>6inchesequivalent diameter.
| | TABLE 5.9-1 LQHPONENT CYCLIC OR TRANSIENT LIMITS COHPONENT I(eactor Coolant System CYCLIC OR TRANSIENT L IHIT l a@in reactor coolant pipe break.Operating Uasis Eartlviuakes 50 leak tests.5 hydrostatic pressure tests DESIGN CYCLE OR TRANSIENT Ureak in a reactor coolant pipe>6 inches equivalent diameter.400 cycles-20 earthquakes of 20 cycles each.I'ressurlzed to 2500 psia Pressurized to 3I07 pslg.Secondary System l steam line break 5 hydrostat,ic pressure tests Break in a steam line>5.5 inches equivalent dl arne ter.Pressurized to l356 psig. |
| 400cycles-20earthquakes of20cycleseach.I'ressurlzed to2500psiaPressurized to3I07pslg.Secondary Systemlsteamlinebreak5hydrostat,ic pressuretestsBreakinasteamline>5.5inchesequivalent dlarneter.Pressurized tol356psig.
| | l4 sic'P)''1L 0 |
| l4sic'P)''1L0
| | ~gp~8,'~~~~n gg~Qe.Zpeat+~SXDtnga, no~>l dined, aS Region 4 7Sfi~he-c.R)vest'~pcs QN<fc~ev nJ~eA~+4v Q-XSCI~~~nk~M 3AS~+V->354uk~ca 4~~Ides>>oo~seeg Q SiSSo NIWD/leans css>>R Bnso>>/'dIsl |
| ~gp~8,'~~~~ngg~Qe.Zpeat+~SXDtnga,no~>ldined,aSRegion47Sfi~he-c.R)vest'~pcs QN<fc~evnJ~eA~+4vQ-XSCI~~~nk~M3AS~+V->354uk~ca4~~Ides>>oo~seegQSiSSoNIWD/leans css>>RBnso>>/'dIsl | | ~cZ f cs>>e>>>>'clme>>t: |
| ~cZfcs>>e>>>>'clme>>t: | | Qns~~~~~vnbnsg U-i>S Q~(ggol1 a.ssc~g~~~~<ot.gs 2-So~ht~il-RRS~~IsscIS ctssnWWI.5,4,2 The tal vater and steam volume of the reactor coolant ayate<ia 12,C12+100 cubic feet as a nominal T of 70 F.5.5 LOOICAL TOWING LOCATION 5.5.1 Thi aateorologica] |
| Qns~~~~~vnbnsgU-i>SQ~(ggol1a.ssc~g~~~~<ot.gs2-So~ht~il-RRS~~IsscISctssnWWI. | | cover shall be located as shovn oa Figure 5.1-1.5,6 FOIL STORACE CRITICALITY SPENT FUEL 5.6,1.1 The spent fuel storage racks are designed and shall be maintained vith: ae A K equivalent to less than 0.95 vhen flooded vith eff unborated vater, A nominal 10.5-inch center-to-center distance betveen fuel assemblies, placed in the storage racks.c, 1.A separate region vithin the spent fuel storage rac3cs (defined as Region 1)shall be established for storage of Vestinghouse fuel Io ce array va INSET~A,S The boundary betveen the Region5'entioned above ea4-oh+~L shall be such that the storage requirement |
| 5,4,2Thetalvaterandsteamvolumeofthereactorcoolantayate<ia12,C12+100cubicfeetasanominalTof70F.5.5LOOICALTOWINGLOCATION5.5.1Thiaateorologica] | | .g shall be castled into Region 2 b: at least, one too as sheen in F'gure 5.6-1.5.6.1.2 Fuel stored in the spent fuel storage racks shall have a maximum nominal fuel assembly enrichment as follovs: Descri tion Maximum Nominal Fuel Assembly Enrichment Vt.'4 235 1)Vestinghouse 2)Exxon/ANF 3)westinghouse 15 x 15 STD 15 x 15 OFA 15 x 15 17 x 17 STD 17 x 17 OFA 17 x 17 V5 4.95 3.50 4.95 4)Exxon/ANF 17 x 17 4.23 COOK NUCLEAR PLANT-UNIT 2 5-5 ANENmZNT NO.5 nMS~p.%S wcug)otgo~9-X3S'gnc2 kacwup A+M~yagtdw to~ho dtgnwtnS Cshpq k~~R~(eog>>sR2Ioogn |
| covershallbelocatedasshovnoaFigure5.1-1.5,6FOILSTORACECRITICALITY SPENTFUEL5.6,1.1Thespentfuelstorageracksaredesignedandshallbemaintained vith:aeAKequivalent tolessthan0.95vhenfloodedvitheffunborated vater,Anominal10.5-inch center-to-center distancebetveenfuelassemblies, placedinthestorageracks.c,1.Aseparateregionvithinthespentfuelstoragerac3cs(definedasRegion1)shallbeestablished forstorageofVestinghouse fuelIocearrayvaINSET~A,STheboundarybetveentheRegion5'entioned aboveea4-oh+~Lshallbesuchthatthestoragerequirement
| | ~d.Iswg~>>g 2.+aaII+>>gtdo>>S doe sgbtse Isa FI~S'-2. |
| .gshallbecastledintoRegion2b:atleast,onetooassheeninF'gure5.6-1.5.6.1.2Fuelstoredinthespentfuelstorageracksshallhaveamaximumnominalfuelassemblyenrichment asfollovs:DescritionMaximumNominalFuelAssemblyEnrichment Vt.'42351)Vestinghouse 2)Exxon/ANF 3)westinghouse 15x15STD15x15OFA15x1517x17STD17x17OFA17x17V54.953.504.954)Exxon/ANF 17x174.23COOKNUCLEARPLANT-UNIT25-5ANENmZNTNO.5nMS~p.%Swcug)otgo~9-X3S'gnc2 kacwupA+M~yagtdwto~hodtgnwtnSCshpqk~~R~(eog>>sR2Ioogn | |
| ~d.Iswg~>>g2.+aaII+>>gtdo>>S doesgbtseIsaFI~S'-2. | |
| ~y* | | ~y* |
| nlLJffIEmperyCfudl~~'<<sava0<a4~c'n"a";3et~eenBeg'ons1and2noae~aKSCsoggU~Qp,p~TQUIT~~5-8~amendment No.
| | nl L J f f I Empery C fu dl~~'<<s av a 0<a 4~c'n"a";3et~een Beg'ons 1 and 2 noae~aKS Csog gU~Qp, p~T QUIT~~5-8~amendment No. |
| IA~rtRIP, DmZa>>~~~~~z~~lÃ5FPAT,5.4.21~nevf941pitstoragerhaaredeailnedandshallbeaatntaedwith+eainal21inchceater-to-center diatancebetnennerfuelblieaauchthatIvillnotexceed0.90rheafuelaaaeRbliea areoffplacedinthepitandaqueousforamoderation iaaaaaaed.5,6,2.2tuelstorediathenerfuelstorageracksahallhanaaaximanoajnalfuelaaseablyenrichment aafollow;1)Vestinghouse 15x15STD15x15OFAMaximumNominaltuelAaaeablyEnrichment Vt.\2354.552)Exxon/ANF 15x153.503)Vestinghous
| | I A~rt RI P, DmZa>>~~~~~z~~lÃ5F PAT, 5.4.2 1~nev f941 pit storage r ha are deailned and shall be aatnta ed with+eainal 21 inch ceater-to-center diatance betnen ner fuel bliea auch that I vill not exceed 0.90 rhea fuel aaaeRbliea are off placed in the pit and aqueous fora moderation ia aaaaaed.5,6,2.2 tuel stored ia the ner fuel storage racks ahall han a aaxima noajnal fuel aaseably enrichment aa follow;1)Vestinghouse 15 x 15 STD 15 x 15 OFA Maximum Nominal tuel Aaaeably Enrichment Vt.\235 4.55 2)Exxon/ANF 15 x 15 3.50 3)Vestinghous |
| ~17x17STD17x17OFA17x17V54.554)Exxon/ANF 17x174.23DRAINAGE5.6.3Thespentfuelstoragepoolisdesignedand'"..allbemaintained topreventinadvertent drainingofthepooLbelovelevation 629'4".CAPACITY5.6.4Thespentfuelstoragepoolisdesignedandsh~allbemaintained vitastoragecapacitylimitedtonomorethan2050iueiassemblies. | | ~17 x 17 STD 17 x 17 OFA 17 x 17 V5 4.55 4)Exxon/ANF 17 x 17 4.23 DRAINAGE 5.6.3 The spent fuel storage pool is designed and'"..all be maintained to prevent inadvertent draining of the pooL belov elevation 629'4".CAPACITY 5.6.4 The spent fuel storage pool is designed and sh~all be maintained vit a storage capacity limited to no more than 2050 iuei assemblies. |
| 5.7CO'.iPONENT CYCLICORTRAVSIEVT LI'.iIT5.7.1Thecomponents identified inTable5.7-1aredesi.gned andshallbe.maintained vithinthecyclicortransient limitsofTable5.7-1.jCOOKNUCLEARPLANT-UNIT25-6A.'KNDMENT NO.,1 V00 4EPCOHPONENT ReactorCoolantSystemTABLE5.7-1COHPONENT CYCLICORTRANSIENT LIHITSCYCLICORTRANSIENT LIHIT200heatupcyclesat<100'F/hrand200cooldowncyclesat<100F/hr(pressurizer cooldownat<200'F/hr). | | 5.7 CO'.iPONENT CYCLIC OR TRAVSIEVT LI'.iIT 5.7.1 The components identified in Table 5.7-1 are desi.gned and shall be.maintained vithin the cyclic or transient limits of Table 5.7-1.j COOK NUCLEAR PLANT-UNIT 2 5-6 A.'KNDMENT NO., 1 V 0 0 4 EP COHPONENT Reactor Coolant System TABLE 5.7-1 COHPONENT CYCLIC OR TRANSIENT L IHITS CYCLIC OR TRANSIENT L IHI T 200 heatup cycles at<100'F/hr and 200 cooldown cycles at<100 F/hr (pressurizer cooldown at<200'F/hr). |
| 80lossofloadcycles.40cyclesoflossofoffsiteA.C.electrical power.80cyclesoflossofflowinonereactorcoolantloop.400reactortripcycles.200largestepdecreases inload.p'IDESI(iNCYCLEORTRANSIENT Ileatupcycle-Tfrom<200'Fto>547'F.CooTdowncycle-Tfrom>547'Fto<200F.Withoutimmediate turbineorreactortrip.LossofoffsiteA.C.electrical powersourcesupplying theonsiteClasslEdistribution system.Lossofonlyonereactorcoolantpump.100KtoOXofRATEDTilERHALPOWER.lOOXto5XofRATEDTllERHALPOWERwithsteamdump.
| | 80 loss of load cycles.40 cycles of loss of offsite A.C.electrical power.80 cycles of loss of flow in one reactor coolant loop.400 reactor trip cycles.200 large step decreases in load.p'I DESI(iN CYCLE OR TRANSIENT Ileatup cycle-T from<200'F to>547'F.CooTdown cycle-T from>547'F to<200 F.Without immediate turbine or reactor trip.Loss of offsite A.C.electrical power source supplying the onsite Class lE distribution system.Loss of only one reactor coolant pump.100K to OX of RATED TilERHAL POWER.lOOX to 5X of RATED TllERHAL POWER with steam dump. |
| VI)0 7Thli~LE5.-i{Conlinuredrn~voNLNT CYCLICORTRRISIENT LiwiTSCOMPONENT ReactorCoolantSystemSecondary SystemCYCLICOATRRNSIENT LllilT1mackinreactorcoolantpipebreak.Operating OasisEarthquakes 50leaktests.5hydrostatic pressuretests1steamlinebreak5hydrostatic pressuretestsnCSlrNCYCLEORTRR[ISIENT Breakinareactorcoolant.pipe>6inchesequiva)ent diameter.
| | V I)0 7 Thli~LE 5.-i{Conl inured rn~voNLNT CYCLIC OR TRRISIENT LiwiTS COMPONENT Reactor Coolant System Secondary System CYCLIC OA TRRNSIENT LllilT 1 mackin reactor coolant pipe break.Operating Oasis Earthquakes 50 leak tests.5 hydrostatic pressure tests 1 steam line break 5 hydrostatic pressure tests nCSlrN CYCLE OR TRR[ISIENT Break in a reactor coolant.pipe>6 inches equiva)ent diameter.400 cyc I es-20 earthquakes o f 20 cycl es each.Pressurized to 2500 psia Pressurized to 3107 psig.Break in a steam line>5.5 inches equivalent diameter.Pressurized to 1356 psig. |
| 400cycIes-20earthquakes of20cycleseach.Pressurized to2500psiaPressurized to3107psig.Breakinasteamline>5.5inchesequivalent diameter.
| | f1, g 0}} |
| Pressurized to1356psig. | |
| f1,g0}} | |
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ML17335A2341998-09-14014 September 1998
Proposed Tech Specs Page 3/4 5-6,revising Runout Limits for SI Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm
ML17335A1931998-08-28028 August 1998
Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000
ML17334B7031998-03-0303 March 1998
Proposed Tech Specs Pages,Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Unit 1 & 2 TS 3/4.6.4 Bases
ML20212A7051997-10-21021 October 1997
Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement
ML17333B0751997-10-0808 October 1997
Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR
ML17333B0451997-09-19019 September 1997
Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
ML17333A9851997-08-11011 August 1997
Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
ML17333A9891997-08-11011 August 1997
Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI
ML17335A2121997-08-0101 August 1997
Proposed Tech Specs 4.7.1.2.g Deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig.
ML17333A8261997-03-26026 March 1997
Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06
ML17333A8301997-03-26026 March 1997
Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions
ML17333A8331997-03-26026 March 1997
Proposed Tech Specs Involving Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted in Prior Amend
ML20135C3781997-02-24024 February 1997
Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements
ML17333A7161996-12-20020 December 1996
Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI
ML17333A7151996-12-20020 December 1996
Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys
ML17333A5161996-07-22022 July 1996
Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge
ML17334B5951996-07-11011 July 1996
Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt
ML17333A4771996-06-19019 June 1996
Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05
ML17333A4651996-06-11011 June 1996
Proposed Tech Specs Re Administrative Controls Related to QA
ML17333A4221996-04-0808 April 1996
Revised Proposed Ts,Moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1
ML17333A3571996-03-12012 March 1996
Proposed Tech Specs,Removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3,4 & 5
ML17333A3301996-02-29029 February 1996
Proposed Tech Specs Re Boric Acid Storage Sys Boron Concentration
ML17333A3231996-02-26026 February 1996
Proposed TS 5.6.2 Re Increase in Max Nominal Fuel Assembly Enrichment Limit,Taking Credit for Use of Integral Fuel Burnable Absorber Matl
ML17333A3221996-02-22022 February 1996
Proposed Tech Specs,Proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor
ML17333A3171996-02-22022 February 1996
Proposed Tech Specs,Modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test
ML17333A3121996-02-16016 February 1996
Proposed Tech Specs Section 3.6.1.6,removing Words Structure & Steel Liner to Be Consistent W/Unit 2 Containment Sys Wording
ML17333A2671996-01-12012 January 1996
Proposed Tech Specs,Modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves
ML17333A2411995-12-19019 December 1995
Proposed Tech Specs 3/4.6.1.2,3/4.6.1.3,3/4.6/1/6 & 3/4.6.1.7,replacing Option a Scheduling Requirements for Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) W/Requirement Per 10CFR50 App J Option B
ML17332B0131995-11-10010 November 1995
Proposed Tech Specs Modifying Surveillance Testing of EDG During Refueling & Normal Operations
ML17332A9991995-10-20020 October 1995
Proposed Tech Specs Adding Exemption to TS 4.0.4 in SR for MSIV
ML17332A9151995-08-0808 August 1995
Proposed Tech Specs Re Deletion of Component Cyclic or Transient Limit Table
ML17332A8751995-08-0404 August 1995
Proposed Tech Specs for Repair of Hybrid Expansion Joint Sleeved SG Tubes
ML17332A8291995-06-30030 June 1995
Proposed Tech Specs Re Fuel Reconstitution,Per GL 90-02
ML17332A8111995-06-20020 June 1995
Proposed Tech Specs Removing Fire Protection Systems from Licenses
1999-09-23
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17335A5581999-10-12012 October 1999
Proposed Tech Specs Surveilllance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases
ML17335A5611999-10-11011 October 1999
Proposed Tech Specs Pages,Correcting TS Pages Inadvertently Submitted in 990923 Submittal
ML17335A5431999-10-0101 October 1999
Proposed Tech Specs Re Containment Recirculation Sump Water Inventory
ML17326A1591999-09-23023 September 1999
Proposed Tech Specs Re Movement of SG Sections in Auxiliary Bldg for SG Replacement Project
ML17326A1461999-09-17017 September 1999
Proposed Tech Specs Pages for Credit of Rod Cluster Control Assemblies for Cold Leg LBLOCA Subcriticality
ML17326A1181999-09-10010 September 1999
Proposed Tech Specs Pages,Revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling
ML17326A0941999-08-17017 August 1999
Proposed Tech Specs,Removing voltage-based Repair Criteria, F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarifying Bases Section
ML17326A1471999-05-28028 May 1999
Non-proprietary Version of Control Rod Insertion Following Cold Leg LBLOCA at DC Cook,Units 1 & 2.
ML17325B6061999-05-21021 May 1999
Proposed Tech Specs Revising Limitations on Positive Reactivity Additions
ML17325B5891999-05-0707 May 1999
Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program.
ML17325B5901999-05-0707 May 1999
Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys.
ML17325B5551999-04-19019 April 1999
Proposed Tech Specs 3/4.8.1.2, Electrical Power Systems & Associated Bases,Providing one-time Extension of 18-month Surveillance Interval for Specific SRs
ML17325B4671999-03-0303 March 1999
Rev 5 to Cook Nuclear Plant Restart Plan.
ML17335A3581998-12-0303 December 1998
Proposed Tech Specs 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases,Reflecting Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses
ML17335A3681998-12-0303 December 1998
Proposed Tech Specs,Adding New TS Re Distributed Ignition Sys
ML17335A3651998-12-0303 December 1998
Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors
ML17335A3621998-12-0303 December 1998
Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos
ML17325B4431998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr
ML17335A4071998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan.
ML17335A2781998-10-0808 October 1998
Proposed Tech Specs Sections 3.3.3.8 & 3.3.3.6,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required
ML17335A2691998-10-0808 October 1998
Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5
ML17335A2651998-10-0808 October 1998
Proposed Tech Specs Changing Containment Sys TS Bases 3/4.6.1.4, Internal Pressure & 3/4.6.1.5, Air Temp.
ML17335A2341998-09-14014 September 1998
Proposed Tech Specs Page 3/4 5-6,revising Runout Limits for SI Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm
ML17335A2301998-09-12012 September 1998
Rev 3 to Cook Nuclear Plant Restart Plan.
ML17335A2721998-09-0404 September 1998
Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project.
ML17335A2751998-09-0202 September 1998
Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly.
ML17335A1931998-08-28028 August 1998
Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000
ML17335A2731998-08-21021 August 1998
Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package.
ML17334A7301998-05-0606 May 1998
Rev 2 of Cook Nuclear Plant Restart Plan.
ML17325B5271998-04-0707 April 1998
Rev 1 to Cook Nuclear Plant Restart Plan.
ML17334B8041998-04-0303 April 1998
Rev 1 to Valve IST Program for DCP Third 10-Yr Interval.
ML17325B5261998-03-0707 March 1998
Rev 0 to Cook Nuclear Plant Restart Plan.
ML17334B7031998-03-0303 March 1998
Proposed Tech Specs Pages,Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Unit 1 & 2 TS 3/4.6.4 Bases
ML20212A7051997-10-21021 October 1997
Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement
ML17333B0751997-10-0808 October 1997
Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR
ML17333B0451997-09-19019 September 1997
Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
ML17333A9891997-08-11011 August 1997
Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI
ML17333A9851997-08-11011 August 1997
Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
ML17335A2121997-08-0101 August 1997
Proposed Tech Specs 4.7.1.2.g Deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig.
ML17333A8301997-03-26026 March 1997
Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions
ML17333A8331997-03-26026 March 1997
Proposed Tech Specs Involving Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted in Prior Amend
ML17333A8261997-03-26026 March 1997
Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06
ML20135C3781997-02-24024 February 1997
Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements
ML17333A7161996-12-20020 December 1996
Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI
ML17333A7151996-12-20020 December 1996
Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys
ML17333A5161996-07-22022 July 1996
Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge
ML17334B5951996-07-11011 July 1996
Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt
ML17333A4771996-06-19019 June 1996
Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05
ML17333A4841996-06-11011 June 1996
ISI & Testing.
ML17333A4651996-06-11011 June 1996
Proposed Tech Specs Re Administrative Controls Related to QA
1999-09-23
[Table view] |
Text
ATTACHMENT 4 TO AEP:NRC:1071N EXISTING TECHNICAL SPECIFICATIONS PAGES MARKED-UP TO REFLECT PROPOSED CHANGES DONALD C.COOK NUCLEAR PLANT UNITS 1 AND 2 9'102250233 PDR ADOCK K 05000315 PDR lpl t vW b Et'al.~n pic 5[467,~C g S I dC~b~~s,~iec ee&dkisiecd kr etnecSc g'~c eii g an cnra4vnce jp 3.CS~0-ASS ec ace cnriedeneeevb'~
d4eve SR'.,uc'cPhbcen&
o-she kk>s]sso KW5/~]and, BX)(oh/PiOF~
+t~~on~PW3 P~~~s'~~t7xlT cL~Lly oc.4 ZSo'~~~<<-S>>%ra iSniS c~u~.b.Ce Za accordance vith the code requirements specified in Section 4.1.C yith allovance for normal degradation pursuant to th>>applicable
$~eillance Requirements, For a pressure of 2485 psig 0 0 Por a temperature of 6SO P, except tor the preaaurixer vhich ia C40 Pe VOLDHE 5.4'5.5 The total contained volume of tho roacto$coolant system ia 12, 612+100 cubic feet at a nominal T of 70 P.avg EMERCENCY CORE COOLIVQ SYSTEMS 5.5.1*The emergency core cooling systems are designed and shall bo maintained in accordance vith the original design provisiona contained in Section 6.2 of the pSAR vith allovance for normal degradation pursuant to tho appl,icable Surveillance Requirements.
5.6 FUEL STORAGE CRITICALITY
-'PENT FUEL e 5.6.1.1: The spent fuel storage racks are designed and shall be maintained vith: a.A k<<eq ivalent to 1.ass than 0:5 vhen flooded vith unborated vater, b~A nominal 10,5 inch center-to-cen:er distance betveen fuel assemblies placed in the storage racks.4%/4FR7 R c.1.h separate region vithin the spent fuel storage racks (defined as Region 1.)shall be established
=or storage of Westinghouse
- ue 4~MSGR 6 CVl The boundezy beeveen the RedionSl".eneioned ebove tee~HL)shall be such that the shall be carried into Regio in Figurc 5.6-1.storage requirement 2 by, at least, one rov as shovn~~AT'Pt: Qt s cof ccneL~caks
~~S.qa vi~occcQ V-ZSS~~g,cdd 4ien 5;SSo gw3/blTO~Con[i~a8ccnat'.~~
i~~~S.+dL cd's<~~COOK NUCLEAR PLANT-UNIT 1 5-5 AMENDMENT NO R~bb.eo.6 I WlesL~o~~4~~g~<Q~+ony~gchlcH~~~5.6 tg l.p,L f I~r t'lA I I I I I I I aegaeon 2 I I I I I I ME+pleuaE Ernpvg Ce~'c" a s V~~-"'<"-ea=:'.a."."=='.".e.-..a"==="": e3.S.c."ace Racks~we.".caen" No.
- I~M+)C~C Z l 0 o~'DESI'XLTTHtXS tuel atored in the spent fuel storage racks shall have~max~aCe&al fuel assembly enrichment aa follon: a 4 t Hasid%Nominal tuel Aaaeably Enrichment 4 235 1)Veatinghouse 15 x 15 STD 15 x 15 OFA 2)Exxon/AHF-15 x 15 4.95 3.50 3)Vestinghouse 17 x 17 STD 17 x 17 OFA 17 x 17 VS 4,95 4)Exxon/ANF 17 x 17 4,23 CRITICALITY-NEV FUEL 5.6.2.1 The ncv fuel pit storage racks are designed and shall be maintained vt.th a nominal 21 inch ccntcr-to-center distance betveen nev fuel assemblies such that k f vill not exceed 0.98 vhcn fuel asscmbli.es are placed in the pit cff and aqueous oam moderation i.s assu.ed.5.6.2.2 Fuel stored'n the ncv f cl storage ra=..s shall have a maximum nominal fuel assembly enrich.=cnt as follovs;Naximum No=.nal Fuel Assembly Enrichment Vt.\235 1)Vcstinghousc 1.5 x 15 STD 15 x 15 OFA 4.55 2)Exxon/ANF 15 x 15 3.50 3)Vcsti.nghouse 17 x 1.7 STD 17 x 17 OFA 17 x 17 VS 4.55 4)Exxon/ANF 17 x 17 4.23 DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent drai.ni.ng of thc pool belov elevation 629'4".COOK NUCLEAR PLANT-UNIT 1 AMENDMENT NO.6
~i L MSZaa Trk~kEI~kCITf f C 4 aN't 1 storage!1 is disig ed and sh il be mi tai ed vith a storage cap city i~ted to no more th n 2050 fuel assemblies.
5 7 SEISMIC C~SIPIChTIOH 5 7,]noae structuree, systems and components in the PS'hall be designed and maintained to contained in the TSAR vith ellovance for normal applicant Surreillance Requirements, identified aa Category I Items original design provisions degradation pursuant to the 5.I NETEOROLOC ICAL TOVER LOChTION 5.8.1 The meteorological tover shall be located as shovn in Figure 5.1-1.5.9 COMPONENT CYCLIC OR TRANSIENT LIMIT+Pl 5,9.1 The components identified in Table 5.9-1 are designed and shall be.maintained vithin the cyclic or transient limits of Table 5.9-1.V COOK NUCLEhR PEDANT-UNIT h.'KNDNENT NO.1 4 1~
TADLE 5.9-1 COHPONENT CYCLIC OR TRANSIENT LIHITS COHPONENT Reactor Coolant Systea CYCLIC OR TRANSIENT L IHIT 200 heatup cycles at<100'F/hr and 200 cooldown cycles at<100 F/hr (pressurizer cooldown at<200 F/hr).80 loss of load cycles.40 cycles of loss of offsite A.C.electrical power.SO cycles of loss of flow in one reactor coolant loop.400 reactor trip cycles.200 large step decreases in load.DES IlaN CYCLE OR TRANSIENT lleatup cycle-T frota<200'F hr>.F.Cooldown cycle-Tfroe>5i7'F to<200'F Hl thout iasediate turbine or reactor trip.Loss of offsite A.C.electrical power source supplying the onslte Class lE distribution systea.Loss of only one reactor coolant pump.lOOX to OC of RATEO TIIEHHAL PNER.100K to 5X of RATEO TllERHAL POHER with steaa duep.
TABLE 5.9-1 LQHPONENT CYCLIC OR TRANSIENT LIMITS COHPONENT I(eactor Coolant System CYCLIC OR TRANSIENT L IHIT l a@in reactor coolant pipe break.Operating Uasis Eartlviuakes 50 leak tests.5 hydrostatic pressure tests DESIGN CYCLE OR TRANSIENT Ureak in a reactor coolant pipe>6 inches equivalent diameter.400 cycles-20 earthquakes of 20 cycles each.I'ressurlzed to 2500 psia Pressurized to 3I07 pslg.Secondary System l steam line break 5 hydrostat,ic pressure tests Break in a steam line>5.5 inches equivalent dl arne ter.Pressurized to l356 psig.
l4 sic'P)1L 0
~gp~8,'~~~~n gg~Qe.Zpeat+~SXDtnga, no~>l dined, aS Region 4 7Sfi~he-c.R)vest'~pcs QN<fc~ev nJ~eA~+4v Q-XSCI~~~nk~M 3AS~+V->354uk~ca 4~~Ides>>oo~seeg Q SiSSo NIWD/leans css>>R Bnso>>/'dIsl
~cZ f cs>>e>>>>'clme>>t:
Qns~~~~~vnbnsg U-i>S Q~(ggol1 a.ssc~g~~~~<ot.gs 2-So~ht~il-RRS~~IsscIS ctssnWWI.5,4,2 The tal vater and steam volume of the reactor coolant ayate<ia 12,C12+100 cubic feet as a nominal T of 70 F.5.5 LOOICAL TOWING LOCATION 5.5.1 Thi aateorologica]
cover shall be located as shovn oa Figure 5.1-1.5,6 FOIL STORACE CRITICALITY SPENT FUEL 5.6,1.1 The spent fuel storage racks are designed and shall be maintained vith: ae A K equivalent to less than 0.95 vhen flooded vith eff unborated vater, A nominal 10.5-inch center-to-center distance betveen fuel assemblies, placed in the storage racks.c, 1.A separate region vithin the spent fuel storage rac3cs (defined as Region 1)shall be established for storage of Vestinghouse fuel Io ce array va INSET~A,S The boundary betveen the Region5'entioned above ea4-oh+~L shall be such that the storage requirement
.g shall be castled into Region 2 b: at least, one too as sheen in F'gure 5.6-1.5.6.1.2 Fuel stored in the spent fuel storage racks shall have a maximum nominal fuel assembly enrichment as follovs: Descri tion Maximum Nominal Fuel Assembly Enrichment Vt.'4 235 1)Vestinghouse 2)Exxon/ANF 3)westinghouse 15 x 15 STD 15 x 15 OFA 15 x 15 17 x 17 STD 17 x 17 OFA 17 x 17 V5 4.95 3.50 4.95 4)Exxon/ANF 17 x 17 4.23 COOK NUCLEAR PLANT-UNIT 2 5-5 ANENmZNT NO.5 nMS~p.%S wcug)otgo~9-X3S'gnc2 kacwup A+M~yagtdw to~ho dtgnwtnS Cshpq k~~R~(eog>>sR2Ioogn
~d.Iswg~>>g 2.+aaII+>>gtdo>>S doe sgbtse Isa FI~S'-2.
~y*
nl L J f f I Empery C fu dl~~'<<s av a 0<a 4~c'n"a";3et~een Beg'ons 1 and 2 noae~aKS Csog gU~Qp, p~T QUIT~~5-8~amendment No.
I A~rt RI P, DmZa>>~~~~~z~~lÃ5F PAT, 5.4.2 1~nev f941 pit storage r ha are deailned and shall be aatnta ed with+eainal 21 inch ceater-to-center diatance betnen ner fuel bliea auch that I vill not exceed 0.90 rhea fuel aaaeRbliea are off placed in the pit and aqueous fora moderation ia aaaaaed.5,6,2.2 tuel stored ia the ner fuel storage racks ahall han a aaxima noajnal fuel aaseably enrichment aa follow;1)Vestinghouse 15 x 15 STD 15 x 15 OFA Maximum Nominal tuel Aaaeably Enrichment Vt.\235 4.55 2)Exxon/ANF 15 x 15 3.50 3)Vestinghous
~17 x 17 STD 17 x 17 OFA 17 x 17 V5 4.55 4)Exxon/ANF 17 x 17 4.23 DRAINAGE 5.6.3 The spent fuel storage pool is designed and'"..all be maintained to prevent inadvertent draining of the pooL belov elevation 629'4".CAPACITY 5.6.4 The spent fuel storage pool is designed and sh~all be maintained vit a storage capacity limited to no more than 2050 iuei assemblies.
5.7 CO'.iPONENT CYCLIC OR TRAVSIEVT LI'.iIT 5.7.1 The components identified in Table 5.7-1 are desi.gned and shall be.maintained vithin the cyclic or transient limits of Table 5.7-1.j COOK NUCLEAR PLANT-UNIT 2 5-6 A.'KNDMENT NO., 1 V 0 0 4 EP COHPONENT Reactor Coolant System TABLE 5.7-1 COHPONENT CYCLIC OR TRANSIENT L IHITS CYCLIC OR TRANSIENT L IHI T 200 heatup cycles at<100'F/hr and 200 cooldown cycles at<100 F/hr (pressurizer cooldown at<200'F/hr).
80 loss of load cycles.40 cycles of loss of offsite A.C.electrical power.80 cycles of loss of flow in one reactor coolant loop.400 reactor trip cycles.200 large step decreases in load.p'I DESI(iN CYCLE OR TRANSIENT Ileatup cycle-T from<200'F to>547'F.CooTdown cycle-T from>547'F to<200 F.Without immediate turbine or reactor trip.Loss of offsite A.C.electrical power source supplying the onsite Class lE distribution system.Loss of only one reactor coolant pump.100K to OX of RATED TilERHAL POWER.lOOX to 5X of RATED TllERHAL POWER with steam dump.
V I)0 7 Thli~LE 5.-i{Conl inured rn~voNLNT CYCLIC OR TRRISIENT LiwiTS COMPONENT Reactor Coolant System Secondary System CYCLIC OA TRRNSIENT LllilT 1 mackin reactor coolant pipe break.Operating Oasis Earthquakes 50 leak tests.5 hydrostatic pressure tests 1 steam line break 5 hydrostatic pressure tests nCSlrN CYCLE OR TRR[ISIENT Break in a reactor coolant.pipe>6 inches equiva)ent diameter.400 cyc I es-20 earthquakes o f 20 cycl es each.Pressurized to 2500 psia Pressurized to 3107 psig.Break in a steam line>5.5 inches equivalent diameter.Pressurized to 1356 psig.
f1, g 0
