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Text

Proposed,Deleted TS Table 3.6-1, Containment Isolation Valves.
	ML17329A619
Person / Time
Site:	Cook
Issue date:	09/24/1992
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17329A620	List: ML17329A619; ML17334B446;
References
	NUDOCS 9210050057
	Download: ML17329A619 (174)
	v • d • e

Attachment 2 to AEP:NRC:1178 Existing Technical Specifications Pages Marked to Reflect Proposed Changes 9210050057 920924'DR ADOCK 05000315 , f" PDR DEFZNZTZONS REPORTABLE EVENT 1.7'VREPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when: 1.8.1 All penetrations required to be closed duz'ing accident conditions are either: a.Capable of being closed by an OPERABLE containment auto>>matic isolation valve system, or b.Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positionsp except pecMkcc~~1.8.2 All ecgxipment hatches are closed and sealed..1.8.3 Each air lock is in compliance with the recpxizements of Specification 3.6.1.3, and 1.8.4 The containment leakage rates aze within the limits of Specification 3.6.1.2.CHANNEL CAZ 1BBATZQN 1.9.A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.The CHANNEL CALIBRATION shall encompass the entize channel including the sensor and alarm and/oz t ip functions, and shall include the CHANNEL FUNCTIONAL TEST.The CHANNEL CALZBRATZON may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

1.10 A (CANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.

This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

(COOK NUCLEUS<PLANT-QNZT 1 1-2~AMENDMENT NO N~Ž~p Qa&~K a~p~~iVre~S

3 4.6 CONTAINMENT SYSTEMS 3 4.6.1 PRIMARY CONTAI PKNT CONTAINMENT INTEGRITY LXMXTXNG CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILXTY:

MODES 1, 2, 3 and 4.ACTION: Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT XNTEGRXTY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .SURVEILLANCE RE UIREMENTS 4.6.1.1 Primary CONTAINMRK INTEGRITY shall be demonstrated:

~~~a~At least once per 31 days by verifying that: '.-.All penetrations*

not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves,.blind flanges, or deactivated automatic valves secured in their positions, except and b.2.All equipment hatches are closed and sealed, By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.*Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position.These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not, be performed more often than once per 92 days.AMENDMENT NO.gg,~Av V~VS glCVOA C~~P~~AMP~A1jlU+TCd.IV%

GOWK(~PNA-~AM+Q~"~i~<COOK NUCLEAR PLANT-UNIT 1 3/4 6-1

L)HITIft6 CQNOI7$0N FGR Or"=PTISAN 3.6.3.1 7+@c".ntain;..ant isolation valve be OPHAoL'E sha1 I The ACTIOll>I pLrC-arLrTY:

t.OO S I, Z, 3 any 4.AC IQY'p~$a EnfA663t satamnt af T/S 3/4.6.3,)fs nat applfcab1e ta the contains'ent

'pur,e sup-ply and exhaust fsalaticn valves, OCR~-th Th Ltf:\INC did f tie (assocfated ACTiGH swtment far these valves fs given fn Technical Speci-ffcatfcn 3/4.6.L.T.

Mfa cae cr mare af the isola.icn valve(s}fncperable, ei~".er: a.Res<re~ie ir.".=erable va1ve(s):o OP'PABLC'ta.as xft!ifn 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , cr b.Isolate eac!i a,=ac.~d penetratfcn wi".h n 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use ai't leut cae ceac:ivated aut"-ztfc valve secured in the isalaticn pasitica, cr c.Esalate c ch af.ec=ecf penetratfca with n 4 hcurs by use af.at leas-cne closed manual valve ar blincf flange, ar d.He in at le*s H07 57~NOSY wi:.",fn.C.".e, nex.6 hcurs and in C"LQ Z:-Wi~QNN wi"in t.".e fallowing 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .(n~pmv(~~~c+~c~cr s,n.<a~f<~~~~~e.SQR'IP LLC lC='FDUIR&c~i 4.6.3.1.1 WQ.fsalat'.cn valv~shall be~emonstrate~

0~+BL>>prior ro recurning the valve eo service aice=a'"ce-nancc, repair or rep'ace=enc choric is per8oz eel on"he valve or its assoc'aced ac"nscor;concrol or pc<<er c'rczi" by per=ounce o"" a cyc~'ng mesc and, ver'-Eicac'on oE ksol.aci"n='=e.g+~mrreek pu.ge.~nb.v~o ad~~J~~~me~be, ops&c>r ud~~~McaMva~e3~k O.C.'Coals.-urn' 3/4 6-14 Ancndacnt.

Ho.

t ue canna w,~e.p W OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by: a.Verifying that on a Phase k containment isolation test signal, each Phase h isolation valve actuates to its isolation position.b.Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.c.Verifying that on a Containment Purge and Exhaust isolation signal, each Purge and Exhaust valve actuates to its isolation position.l~(~EC A 4.6.3.1.3 The ieolaeion aioe of each paver opezaead oz aveoaaai)valve of-hehha-MM shall be determined to be vithin its limit vhen tested pursuant to Specification 4.0.5.COOK NUCLEAR PLANT-UNIT 1 3/4 6-15 AMENDMENT NO.444 e

VAI Y(: tt((HI)C A.PllR" I"A" ISOLATlON TAALE 3.6-1 CO)(lbl(NEI(1 1SOLhT ln(l VALVES FHllL'T ION 1SOI.A3.ION T lHC.INrSLCONDS 2.l.I ,I (r.y.9 1().11.13.14.IP 16.17.IA.1 I)2().21.22.23.24.2J 2c).Crit-4~i S (:(:(t-4!i6 r.r.((-4.I t.l lt-4()().r I tt-)ri2 Ilt'.lt-2()l Il(:It-2()2 I)('.lt-P()3 I)('.lt-2()4 I)(:It-2()!i I)CIt-206 I)(:It-2D 7 I)(:it-301

.I)rlt-1()2

()(:It-303 I)(:It-304 I)f:It-310 l)C(t-320 I)(.II-3 30 I)(:lt-340 DCIt-600 ()CA-Cnl I)(:0-610 t)C(t-611 I)(:It-C?n l)C(t-621 CgH to Reactor Srrpnorts CCfl+roxr Relic tor Su>>por t s CCII f Nor t Aeac tor S<<plrnr.t s CCI-I froxl Concuss 1 trlrr.Ilx.CCW to CxceAs~l tr)>>.Ilx.R.C.Drain Tank lo Vu>>t.Ililr.A.C.Drain'la>>k to~Chas Analyzer R.C.Drain Ta>>k to Vee)g.Ili)r.It.C.Drain Tarrk to Gas A'r>glyzer A.C.Drain Prrorn S<<ction Isol~tit)II.C.Drain Purxn Suction Isola>jorr I(2 Supplv to A.C.Drain lagk Steam Cieneratnr Alowrlawr)&ample Ill Steam Ge<<erator Alowrpf wn Sample I)2 Steam Ge>>erator Alyiilown Sample l3 Steam Generator ATowrlowr)

Sa<<rple l4 Steatll Cielrerator Alowrlnwn I irres ll Steaor Generator Alowrlowr)

Lines l2 Stedf)r Gy>>erator Alowriow>>Li>>es l3 Steay-Ger)era tor Alowrlown Lines l4 Cr)ntainment Sump to llaste I(olrhrp Co>>l.a inmer)t Sump to i(as te Iloldrrp ice Conde>>ser Drain to Drain Ilrlr.ice Condenser Drain to l)rain Ildr.Contin<<orrs Verrtllation Drain to lloldup Continuous Ventilation Drain to Ilolrlup 10 ln 1(l lr)10 1()10 ln 10 ln ln ln l()10 10 ln)o~-ln ln lfl ln 10 yhi.VE)IIIIIAEA ThALE 3.fi-l COllTh I tIHEtlT I SOLAT l All VALVES f IIII CT ION ISOI+ION TINE i SECnHDS h.l.2.3.I'i 6.7.n.rJ)n.Il.)2.13.14.I r16l.)7.I I).19.20.21.22.2'3.24.2rJ~26.Cf A-4r65 Cf It-456i r.CA-4>7 c(.lt-46)n Ct: It-4(i2 I)CIt-2I)1 l)CII-202 I)f.it-2I)3 l)ctt-204 DCA-2I)".)

DCA-206 I)CIt-207 DCA-301 l)cA-302 DCII-303 1)cA-304 I)CI\-31 0 I)CA-320 DCA-330 l)CA-340 l)CA-600 l)CA-601 DrA-6ln Irt:It-61 1 l)r.it-G?0 l)f A-621 I'llhSE"h" ISOLhTI N CCCC~to haactor Supnarts CCfl frorrj Iteactor Supports CCII from>Abactor Supports CCII frorr)C)tcess 1 tdn.Ilx.CCW to Excess~ltr)n.

Ilx.A.C.Drain Tank ta Yent.IIrlr.A.C.Drain Tank to Ctqs hnalyzer fI.C.Drain Tank to V~en'g<llrlr.A.C.Drain Tank to Gas hnzlyzer A.C.Drain Prrrrrn Suction Isoigtlon A.C.Drain Purrrn Suction Iso)'at:ion II2 Supply.'t.o A.C.Drain~Tdnk Stearrr Cienerator Olowd))w~h Sample Nl++>>Steam Ger)erator ftlypdown San)I)le 82 Steam Generator Al'owrlown Sarirple P3 Steam Generator I)lowdown Sarrrple P4 Stearrr Gerje~rtor Dlowrlown Lines rl'I Stearr)Generator Olowdown Lines II2 Stearri Gei)erator Illowdown Lines II3 Stye m Generator Dlowdown Lines E4 ontalnr)rent Sump to Ilaste IIoldrrp Contalnrrrej)t Suvrp to llaste Iloldup Ice Conrlenser Drain to Drain lldr.Ice Condenser Drain to Drain lldr.Continjrorjs Ventilation Drain to Iloldup Continuous Ventilation Drain to lloldup 10 10 In I I)ln.10 ln ln 10 ln ln 10 1 I)10 10 10 10 10 In IO'.Ill 1II~

Thl)I.E 3.6-l (Cnilt ln>>ait)VAI.VE IIIIIIAI It VCR-la Et:It-I I'Qlt-I 2 Et:II-.I 3 Et:}I-I&4-..

v.rn-l5 VCtt-l6 L'I:It-I?V.Ctt-l I)Et:It-I9 Et:tt-20 V.t:It-2 I Ertt-22 Et:tt-23 Ctt-24 L'I:It-25 Et:It-26 ECR-2?Et:It-28 Et:It"29 Et:tt-416 IXtt-4il?L'I:It-496 Et:tt-497 V.t:It-535 Vntt-536 rtclt-3I)I OCtt-314 ICB-5 1 t:It-6}tr.tt-251

}tt:tt-2}tt:t 53.I"254 CB-II)5 ctt-ln6 7.2I)-29.3n.31~32.33.34.35'6.37.38.39.4n.4).I 42.43.44~45.46.47.49.50.51.53.54.55.56.57.56.59.h.plliNE"h'ttttrTIntt

'Gnl.hTI~I)II Cont}niiei)}'unt.112 Sample Return Ciint.1)2 Snaiple-hlr to}tee.K Coot.112 Snmple-hlr f rom}tee.E C>>>>t.112 Snmple-I.ou.Cont.Vol.Cant.II2 Sample-I.ou.Co>>t.Vol.Cont.1)2 Sump)a-ltp Coiit.Vol.~, I:o>>t.It Sum)i)c-11p I:u>>t.Vol.opt.112 Sump)c-hlr tu Itcc.M CuiiM It.Sumplc-hlr fr<<m Itcc.It Cont.)12 Suiiip)e-Co>>t.}tume Val.Cont.II~Sniiip le-Retiirn Cant.11 Sn'mplo-hlr t.o Rcc.E.Ca>>t.112 Sai pic~~hlr fr.ttcc~E I:u>>t.II Suiiiplu-I.uu Cont.Vol 2 Co>>t.It Sump)e-I.>>WCo>>t.V'I.Cont II Suwip le ltp Coiit.ol~Cant.1)2 Suiiiple-Itp Coig.Vql.Caiit.11 Sam)i)a-Alr/o tt<<c.~)i.Ca<<t..II2 Sample-h,v I'r.It<<c.)I".~~Coiii.II Sample-,'ant.I)<<mu Vul 2 I'AS Coillnl mac>>t iiwti Sump)c I'hS Cuiitntiimcii S<<mli Sump)u I'AS)taut<>l Cua Iti:t>>rn I'AS)Iauty:I.I

~I>>ld ni<<l G<<s!tet>>rii I'hS I:io)falnmc>>t Guu Sumplc I'AS+il>>t nl>>mc>>t.ttnu Sump)c lt~>wptily to I'reun>>riser Relief Tank I(>Siipply to hcciim>>)utoru hcciim>>1 utors Snwip)c Acc<<ai<<lutnro Sump)c SaNI>le I.1 iie f rum Steam Cu>>.O<<t lct l I Sum)i)a I.l>>c from Steua t4.>>.Oiitlet!2 Samtilc I.liiu friim Steam t)c>>.A<<tlat J3 Snmlilc I.I>>c tnrm Stcam Ocn.tiiitlct I4 ltut I.c};Siuaiplu lt>>t I.clt Suiiip)c 1SOl.hTIOII Tl}IE 1tt SECnttt)S 0 ln 10 ln ln I I)10 IO ln IO IO IO I I)I I)lt)ln In ln IO)n I I)lt)ln 10 It)IO In.IO n n 0 0 IVALVE NUMBER FUNCTION TABLE 3.6-1 Continued ISOLATION TIME IN SECONDS A.PllASE"A" ISOLATION Continued 63, 64.65.66.67.68.69.70.71.72.73.74.75.76.77.78.79.80.81.82.83.84.NCR-107 N 8~108 NCRM NCR-110 NCR-252 PCR-40 QCM-250 QCM-350 QCR-300 QCR-301 QCR-919 QCR-920 RCR-100 RCR-101 VCR-10 VCR-11 VCR-20 VCR-21 XCR-100 XCR-101 XCR-102 XCR-103 B.PllASE"B" P RZ Liquid Sample PRZ Liqui.d'ample PRZ Steam Sample..PRZ Steam Sample, Primary Water to Pressure Relief Tank Containment Service Air RCP Seal Water Discharge ,RCP Seal Water Discharge egdown to Letdown Hx.Letdown to Letdown llx.Demineragized Water Supply for Ry cling Deminerall'zqd Water Supply fo~Refueling PRZ Relief Tank to Gas Ana~PRZ Relief Tank to Gas Anal.Glycol Supply to Fan~Cooler Glycol Supply to Faa Copier Glycol Supply from Fan Cob er Glycol Supply~~from Fan Coole Control Aj./+to Containment re Control'Air to Containment Isolatio Contro Air to Containment Isolation ntrol Air to Containment C ISOLATIO Cavity Cavity 10 10 10 10 10 10 15 15 10 10 10 10 10 10 10 10 10 10 10 10 10 10 l.2.e 6 rt u)8.tA 10 CCM-451 CCM-452 CCM-4+5 CCM-4-458 CCM-459 ECR-31 ECR-32 ECR-33 ECR-35 I:CR-36 CCW from RCP Oil Coolers CCW from RCP Oil Coolers CCW from RCP Thermal Barrier CCW from RCP Thermal Barrier CCW to RCP Oil Coolers&Thermal Barrier CCW to RCP Oil Coolers&Thermal Barrier Containment Airborne Radiation Monitor Containment Ai.rborne Radiation Monitor Containment Airborne Radiation Monitor Containment Airborne Radi.ation Moni.tor Containment Airborne Ra<~<ion Moni.tor 60 60 30 0 6 60 10 10 10 10 10

~-

~r 8~~~t~'I~n n Cl CI O FIIHCYlnt I~Vhl.VE IIHIIIIElt I tthSF."ho 1S'.h.12.l3.14~15.16.17.In.l9.20.21.22.23~24.25.26.27.28.29.3n.31.32.33.34.35~3&.37.38.43.uCR-9nl uctt-903 uctt-9n5 uI:II-907 MCII-9n9 ucn-911 III:R-913 ucn-9I5 ucn-92I'HCR-923 iICR-925 IICR-927 MCR-929'HI:8-931 ucR-933 IICR-935 MC.II-941 HI:8-942 ll CII-943 ucR-944 urR-945 HCR-946 HCII-94r 7 HCII-948 ucR-95l ucR-95 Men~953 LII-954 I:It-955 CR-956 ucR-957 HCII-958 A I~ATIGll Cnntrnuel}

>NFSM to I~u Cantainracnt Vent ll NL'SM fram l~u Cantaloment Vent II HI'-SM.to I.au Cantalnmcnt Vent l2 HESM from I.ou Cnntalnraent Vent l2 tlL'SM to I.au Containment Vent l3 IIESM from l,ou Containment Vent l3 ltESM to l.ou Containment Vent l4 tlESM from l,ou Containment Vent l4 HESM to tip Containment Vcot I I tlESM frora Hp Contatnrat}nt Vent lg tIESM to Hp Contatnmcnt V'cnt i2 tIL'SM frora ttp Contalrrmcnt nt l2 HESM to Hp Caotulnmcnt Vent l3~.IIL)SM from Hp Carrtatpra6nt Vent l.HESM to Hp Contut~mcnt Vent l4 Hl SM fraar Hp Cprftatnment Vent 14 HLSM to RCP Hotar hlr Cnaler IIESM ta IICP Hotor hir Cooler IIFSM te IICP Hotar hlr Cooler HLr!pi.-to ltCP tlotor hlr Cooler jEslt from RCI'otor hlr Cooler~IIFSM from RCI'otor hlr Cnalcr HESM from RCP Hator hir Cooler HESM from RCP ttotar hir Cootur HFSM to RCP tlotor hlr Cnolur Vent II tH Sll ta IICP tlotor hlr Cooler Vent l2 IIESM to BCI'otor hlr Cooler Vent l3 IIESM to RCI'ntor hlr Cooler Vent l4 IIL'SM fram RCP ttntar hlr Coa)er Vent Il HL'SM frora RCP Hotur hlr Cooler Vent l2 HESll frora IICP tlatar hlr Cooler Vent l3 HESM from IICP Hutor hlr Cooler Vent/4 1snuvtntt YIIIE f~t SF.mt ns In la IO ln ln In la Ia ln In tn ln ln tn ln In la Ia ln la la ln IO~fo IOg ln Ia tn I'a I'a I'a VhLVH)NHBER I'UNCTIOII Thfll.E 3.6-1 (Cont In>>ail)IGOLATIO'.I TIME Ill SECQNOS P IPSE>>D>>ISOMTIOII Continued n O P4 I~g4 lg o Vl WCR-96'1<ICIL-963 HcR-965 WCR-967 HCR-900 HCIL-902 VCR-904 WClt-906 1JCR-900 IJCR-910 WCR-912 HCR-914 WCft-920 WCR-922 WCft-924 IJCR-926 44'5.46.47'Q~49~50'1'2~53~54.55.56'7'8'59~'I JCR-920 60..IJCR-930 WCR-932 1 J Clt-9 34 IJCR-960 62'3'4'5'6'7'CR-962 IJCIL-964 HCR-966 C.CnllThllll fE VCR-101 VCR-102 VCR-103 VC$~104 eft-105 VCR-ln6 VCR-107>VCfl-201 Vcll-202 Vcft-203 1~2~3~4~5~6.llESIJ to Instr.Bm.Hant Vent IIESH from Instr.Rm, Heat Vent IIISH to Instr.Bm.East Vent llESW from Instr.Bm.Hast Vent 1/ESI)to BCI'oucr Containmcnt Vent Pl IJESIJ~fram l.aucr Containmcnt Vent 01 1IESII to RCP Louar Containment Vent P2 1JESIJ f rom,.l.ouar Coiitaiiimant Vent t2 lJESIJ to BCP~,Loucr Containment Vent J13 llESIJ from Lou'cy Containment Vent P3 IJESW to RCI'oueg Containmcnt Vent P4 ill'.Sll from Loucr Coqtainmant Vent P4 IJESLJ to RCP llppcr Cantainmcnt Vent 41 llESH from llppcr Cantaknqcnt Vent Pl lJESW to RCP lfppar Cantainmcnt Vent~82 IJESLJ from Ifppcr Cantainmant VcnJ~I2 l!ESLI to RCP lfppcr Cantainmcng<Ucnt P3 llESW from tipper Containmcpt-Vent Ig, NESIJ to RCP llpper Containmcnt Vent 74..llESLJ fram llppcr Contalnmcnt Vent d4.IIESIJ to Instrument>Roam East Vent~llESW from Instrument Boom East Vent llESlJ ta Ins triiman t Roam Hcs t Vent llESll frog<Instrument Boom Hast Vent llT PIIRflE.hl1D EXIIAIIST Ak Instr.Boom P>>rge hir Inlet I>>str, Room Purga hir Out'let Louer Comp.Purge hir Inlet l.ower Comp.Purge hir Outlet llppar Comp.P>>rpa hir Inlet llppcr Comp~Purge hir Outlet Cont.Press.Relief Fan Isolation Inotr, Baom Piirf',a hir inlet Instr.Roam Purge hir Outlet~0~1.niict Comp.P>>rf',c hir?nlat 10 10 10 0 10 ln 10 10 10 10 10 10 10 lfl 10 10 10 10 10 10 10 10 10 ln 5 5 5 5 5 5 0 TABLE 3.6-1 Continued 0 0 0 I C LVE NUMBER C.C NTAINMENT PURGE 12.VCR-20 13.VCR-206 14.VCR-207*FUNCTION EXllAUST Continued**Upper Comp.Purge Air Inlet Upper Comp.Purge Air Outlet Cont.Press Relief Fan Isolation ISOLATION TIME IN SECONDS A'5 D.MANUAL ISOLATION VALV 1.ICM-111 2.ICM-129 3.ICM-250 4.ICM-251 5.ICM-260 6.ICM-265 7.ICM-305 8.ICM-306 9~ICM-311 10.ICM-321 11.NPX 151 VI 12.PA-343 13.SF-151 14.SF-153 15.SF-159 16.SF-160 17.SI-171 18.SI-172 RHR to R gold Legs RHR Inlet toOPumps Boron Injectionnlnlet Boron Injection In%t Safety Injection Inle Safety Injection Inlet RHR Suction from Sump RHR Suction from Sump RllR to RC Hot Legs RHR to RC Hot Legs Dead Weight Tester Containment Servic Air Refueling Water+pply Refueling Water Supply Refueling+Aity Drain to Purification System Refueling Cavity Drain to Purification System Ssfe~c Injeceicn Tese Line Ac umulator Test Line NA NA NA NA NA NA NA NA NA NA HA HA NA NA NA NA HA HA Vh}.VE)ill)IIII R EISICIISII Thill.F.3.S~lCont inucd}ISOLATIQII Tll<E I II ECOlmS llh IIA)Ih llh llh llh llA IIA II A IIA llh Il.Hh)lllhl.7SA}.hTIO)I Oh}.VRS Continued}

(})}9.CCR-440 CCM from)}sin Stcaa Penetration 20 CCR-44l CCM from lt'sin Stcam Penetration 2}o llCll-22}Hain Steaia to~huxlliory Feed Pump 22~Ilk)i-23 I}lain Steaa to hugillsry Feed Pump 23 I CCII-Ii 30 CCll to Kaat Preasur~Equa}Ization Fan 24'C)I-43}COI from Fast Pressure<~Equalizationgan 25~CC)I-432 CCII to linet Creeaore Eqiiciltatlon I'an 26 C(3I-433 CCM from}lest Prcssure kquu};iz tion Pan 27.Skl-BA Upper Containment S>>mp}e 2S~SII-10a Upper Containment S>>IIIp}c>~29~Skl-4~Instrument Room Sample~" 30.S)I-6a Instrument Roaii SaappEk llh-)lanual Valve-Isa}ation time not app}icablo~(I)Inclcilca abator opcrateil veloce vltlch 4o not leolate antooatlcally.)lay bc opened on an intermittent basta under administrative control-Contapkaent purge supply,and exhaust isolation yslves (VCR-101 throuPh l06 an&<VCR-201 through 206)easy ba opened under Technical Specification 3/4.6.1.7.

CONTAINMENT SY~i BASES 3/4.6.2 OEPRESSURIZATION ANO COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray sys em ensures that contain-ment depressurization and cooling capability will be available in the event o a LOCA.The pressure reduction and resultant lower containment leakage rate are consistent with the"assumpticins used in the accident analyses.3/4.6.2.2 SPRAY AOOITIVE SYSTBl The OPERABILITY of the spray additive system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA.The limits on NaOH minimum volume and concentration, ensure that 1)the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2)corrosion effects on components within con-tainment are minimized.

These assumptions are consistent with the iodine removal efficiency assumed in the accident analyses.3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment

'isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.

Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the nalyses for a LOCA.3/4.6.COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systans required for the detec ion and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flanmable limit during post-LOCA conditions+

Either recombiner

'nit is capable of controlling the expected'ydrogen generation associated with 1)zirconium-water reactions, 2)radiolytic decomposition of water and 3)corrosion of metals within containment.

0.C.COOK-UNIT 1 8 3/4 6-3 Insert A: The opening of containment purge and exhaust valves and locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations:

(1)stationing a qualified individual, who is in constant communication with control room, at the valve controls, (2)instructing this individual to close these valves in an accident situation, and (3)assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.

DEFINITIONS REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73~CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when: 1.8.1 All penet ations required to be closed during accident conditions are eitherr Capable of being closed by an OPERABLE containment automatic isolation valve system, or b.Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, 1.8.2 All equipment hatches are closed and sealed, 1.8.3 Each air lock is in compliance with the requirements of Specif ication 3.6.1.3, ,'e I r~pl 1.8 4 The containment leakage rates aze within the 1$mits of.Specification 3.6.1.2, and J\The sealing inechanism associated with each penetration (e.g., welds, bellows or O-rings)is OPERABLE.CEASEL CALIBRATION 1.9 A KDHNPZ CALIBRATION shall be the adjustment, as necessary, of the-" channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.The CHANNEL CALZBRATZON shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.The CQDQiNEL CALIBRATZON may be performed by any series of sequential, overlapping or total channel steps such that the entize~channel is calibrated.

CHANNEL CHECK 1.10 A CHANNEI CHEcK shall be the qualitative assessment of channel behavioz during operation by observation'.

This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring t: he same parameter.

1-2 COOK NUCLEAR PLANT-UNIT 2 AMENDMENT NO 7g 7 g~~~~~Uqg~~CA('A'iMM fYU44&p+p gl 3 4.6 CONTAINMENT SYS~3 4.6 1 PRIMARY CONTAZ~NT CONTAZNMENT ZNT GRZTY LZMITING CONDITION FOR OPERATXON 3.6.1.1 Pzimary CONTAXNMENT ZNTEGRXTY shall be maintained.

APPLICABILITY:

MODES 1, 2, 3 and 4.ACTION'ithout primary CONTAINMENT INTEGRITY<

restore CONTAXNMENT INTEGRIT within one hour or be in at.least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .SURVEILLANCE REQUZ~~NTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated.

a.At least once per 31 days by verifying that: 1 All penet ations<<not capable of being closed by OPERABLE.;...containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except~eM~W~a'~~and 2.All e~ipment hatches are closed and sealed, b.By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.<<Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position.These penetrations shall be verified closed during each COLD SHUTDOWN except that such veiification need not be performed more often than once per 92 days.Q~~~pQ.~LL;AQ~~'~'L&~~kl/+

Cndem(~peen~~~nu~~%i~4an 5 h 3', COOK NUCLEAR PLANT UNIT 2 3/4 6-1 AMENDMENT NO 144

~6 3 f4.6.3 CQH j AI~EN j ISOLn7IOH VALVES~~LIHITING CQHOITIOH FOR OPERATION Zaah 3.6.3.1 Re-cantonment fso1atfcn valve~pecH'ied i-.sha11 6 EAEEAEL'6"66-: '.ll Altt 6 stateaent af Technfca1 Speci ication 3(4.6.3,>fs nat applicable ta the cantaf anent purge and exhaust,fso1atfon va1ves, The l.fmftfng Candftfon or Operation and its associated'CTION statenent for these valves"~given fn Technfcal Specfffcatfan 3/4;6.1.7.

, o.APPLICABILITY:.

Modes I, 2.3 and 4.>cnaH:-csMAee+~~Nth one ar'are of the salatfon valves(s)fnaperab1e, mafntafn at least one fsalatfan valve OP~LE in each affected penetration that is aoen and either: a.Restore the fnaperable va1ve(s}t0 OPBABLE sa us~fthfn 4 haurs, or b.Isolate each affected penetration Hthfn 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months hy use of at least ane deactivat d autamatic.valve secured in Ne isolation pasftfan, ar CE c.Isolate each af ected penetration Nithin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at 1eas one c1ased t"znua1 va1ve cr blind f1ange;or d.Be in at 1~t HOT 57~(CSY within De nex 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and in COLQ SiiUTj.QMH within the follawing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .7~~P~L'~~c'r~

~4 GP~~QicW~~

a.o 4 are.noh cyylimh'e.

SURVKIL&jHC:-

REQU IRH<BG S'6.6.l...l 4t 6 t ll t~~.'.*tt.'enans rated OP:WBLj.prior a wturr,ing the valve ta service af.r maintenance, repair oz~ulacj.nent work is per=anted on>e valve or its associated ac uat"r, cantml or p~er circ"i'y perfcj...one or a cycling"est and verfffcaticn of isola ion~--e.Qodaunm~a mWv~o aK Sek&a'w4<~~~MV~~Qt C5p~~OA~lAAK~A~D~~u W6~~@qjA~4m.WV<~&CO k.Q C CQ'(-lj'iI j 2 3/E'~~CEEen 1~.t~ii".

COÃ1'AILMENT SY~r SURVEILLANCE REOUI.'KNTS Continued 1'v~~S%iME>~4.6.3.1.Z Each/$solacion valve shall be demonscraced OPERABLE during the COLD SHUTDOWN or.REFUELING MODE ac least ance per 18 months by:~J a., Vexifying that on a'Phase A containment isolation test signal, each Phase A isolacion valve actuates to its isolation position~'\~b.Verifying chat on a Phase B cantainmenc isolation test signal, each Phase B isolation valve actuates co ics isolation position.c.Verifying that on a Containment Pux'ge and Exhaust isolation signal, each Puxge and Exhaust valve actuates to its isolation~+~@,~MD, 4.6.3.1.3 The isolacion time of each paver apexaced ox'utomacic%alve o&-to Specification 4.0.5~~~~~o>>~e>>~>>>>>>>>>>>>v~r~~>>~~~>>~'I 1 v~>>>>>><~rCOOK NUCLEAR PLANT-UNIT 2 3/4 6-14 mENDmK NO/7 WM,

n VALVE HUHBER TABLE 3.6-1 CONTAINMENT ISOLATION VALVES FUNCTION ISOLATION TINE IH SECONDS I c A.Ol I Cft PHASE"A" ISOLATION 1.CCR-455 2.CCR-456 3.CCR-457 4.CCR-460 5.CCR-462 6.OCR-201 7.DCR-202 8.OCR-203 9.OCR-204 10.OCR-205 ll.DCR-206 12.OCR-207~t C CW to Reactor Supports CCM from Reactor Supports CCW from React Supports CCM from Excess ltd Hx a y~e~CCM to Fxcess 1 tdn.x.R.C.Drain Tari to Vent.Hdr.D.C.Drain Tank to Gae Analyzer D.C.Drain to Vent Ildr.R.C.Drain Tank to Gas Analyzer'.C.Drain Pump Suction Isolation R.C.Drain Pump Suction Isolation H2 Supply to R.C.Drain Tank<10<10<10<<10<10<10~<10<10 10 10<10 TABLE 3.6-1 ,ga y g~I~;~n C)fi VALVE NUHBEA I c A.PllASE"A" ISOLATION 1.CCA-455 2.CCR-45C'.CCR-457 4.CCR-460 5.CCA-462 6.DCR-201 7.DCA-202 8.DCA-203 9.DCR-204 10.DCA-ll.A-206 1.DCA-207 CONTAINMFNT ISOLATION VALVES FUNCTION ,>*Ii, Ulltii.'ll.!ii.;.:

'CCW eactor Supports CCW from Rea r Su p rts CCW from Reacto S rts CCW from E ess ltdn.fix.CCW t Fxcess ltdn.Hx.).C.Drain Tank to Vent.Ildr.s>~I A.C.Drain Tank to Gas Analyzer A.C.Drain to Vent Ildr.R.C.Drain Tank to Gas Analyzer R.C.Drain Pump Suction Isolation A.C.Drain Pump Suction Isolation N Supply to R.C.Drain Tank ISOLATION TIHE IN SECONDS<.10<10<10<10<10 10 10<10<10<10<10<10

.~J I J~J~ii.'~i~l)h ln D~C u>9 I il.TAOLEl.3.6-1 (Continued)

COHTAIHHEHT ISOLATIOH VALVES VALVE HUHDER A.PllASE"A" ISOLATION 13.OCR-301'4.

OCR-3028 15.OCR-3034 16.OCR-304>>17.OCR-3108 14~,~$il'y.S~~g~FUNCTION iJ y-~I iJ (J.(Contin d)Ste q Generatot 8'lowdown Sample~~j Steam Gen ator Glowdown S>le N2 Steam Generato Glow n Sample 83 Steam Generat lo own Sample N4 Steam G rator Dlowdown nes Il ISOlA N TINE SECONDS J I~,<10<10<10<10<10 la.DCR-320k 19.DCR-3304 20.OCR-3404 21.DCR-600 22.D 601 OCR-610 24.'CR-611~~S m Generator Glowdown Lines 2 J Steam Generator Dlowdown Lines II3 S team Genera tor Dl owdown Lines N4 Containment Sump to Haste lloldup Containment Sump to Waste lloldup Ice Condenser Drain to Drain Ililr.I c e Condenser Drain to Drain Hdr.<10<10<10<10<10<10

~~.s..".,-TABLE'.3.6-1 (Continued)

CONTAI HHEHT ISOLATI OH VALVES M~C7l I O CO VALVE HUHDEA A.PIIASE"A" ISOLATION 25.DCA-620 26.OCR-621 27.ECA-10 20.ECR-.ll 29.F.CR-12 30.ECA-13 31.ECR<<14 32.FCR-15 h 33.ECR-16 34.-ECR-17 35.EC ECA-19 I2-Sample-II2 Sample-~*II2 Sample-II, Sample-ll2 Sample<<Los.Cont.Vol.Con Up.Cont.Vol.Up.Cont.Vol.Cont.Cont;Cont.Cont.Air to Aec.M Air from Bec.'H Cont.Dome Vol, Cont.II2 Sample-h FUHCTIOH~-'." i'Contlnuedgl" p Conti uous Ventilation Drain to Iloldup!'s Continuou ventilation Drain to Ilold Cont.II2 Sampl return j Cont, ll2 Sample-A)ec, E Cont.II2 Sample lr Froid~Roc.

E Cont.II2 S pie-Lou.Cont.Vol.-ISOLATION TIHE IH ECOHOS<10<10<10<10<10,<10<10<10<10<10 COIITh>>AIFIIr Isnl>TIOII vhI.VEs ECft-20 ECR-2l 40.n C3 Cl C M At:tt-2II 42.ECA-26 ECR-27 LJ l~~M CRl I IER Ii 5.47~4D~49.5n.'5 I.'52 i 53.54.O~~Vhl VB IltAIAEA PIAICTlotl

~l.'n.i-'-~~r ptlhSIr."h" IIJOIATIOII tCont lnrieil)..:.".."~I~~~31~Conti II2 Sample-Iteturrl I)I'D.Cont.II2 Sarnpl~-hlr t,o Bac.II, 29.EClj-22 Cnnr.II2 Rnnplll-hlr'Fr, Rnn.E FCA-23-Ciini, ll2 Sample-l.u.Cont~~Vol.~<, 41.Cont II2 Sample<<),nir-'CBlrtn Vol.~LCA-25 Cont.II2 Sample-ttp.Cont'.43.Cont~II2 Sample-lip.C t.Vol;r l/I li~Coiit.II2 Saniple-4r ta Rcc.M.I!Ctt-20 Coiit.II2 Gamp-hlr I'r.Bcc.M.'46.Enlt-29.-.-Cnnt..II2 mple<<C<<<<ti Ilorne Vol~VCA-4I6hS Co talniaont.

S<<mp Sample gott-4l 7 PhS nota lnniiint S<<rnp Santiln ECtt-496 Mjiate I.lrtulit a<<d Ciae ttcturn.FCtt-497 Phs Ilaete Llit<<ld nnhl Cno Itcturn 9 Kntt-53$Phs Contnl<<lnaiit naa Sample ECtt-536 Phs Cnntal<<inoiit liaa Siinjljle ct:tt-30 ll2 S<<pply to Prcaaurlrcr Rillef Tank CCA-4 II2 Siipply to hcc<<m<<latore ISOIATlntl TIIlE~III sRcntms tin<IO cln itn cl 0 BIO~el 0 cIO cln ct 0<IO<IO<<I 0<<tn cln<In~I A n-i~~\S I i , TAOLE 3.6-1 (Continued)

COATAI)lllEHT ISOLATIOll VALVES ,)I 8 VALVE))UHGER i A.P))ASE" ,55.1C 63.))en-los I)CA-la)64.)lCR-lan.ot Leg Sample ,-.PAX Llquld Sample Ib O'Zi~~i j PAZ Llqitld Sample:,, FUIICTIOII

""'i'" ISOLATIOl<(Continued)...., R-5...Accumulators Sample\"~(1CA-6:;.Accumulators Sample~5>))CA-25II Samp'e Line from Steam i klCA-252l Sample Lt from St 59.)ICA-253 J Sample Line fr Stcam.60 IlCA-254k Sample L)frsa Stc i 6l))CA-105 I)ot g Sample C;Outlet fl Gen.Outlet Jl Can.Outlet l3 Can.Outlet l4 ISOLAQ)TIHE I PEECOihOS<10<10<10<10<10<10<10<la<la<10 n rt O 00 65.a CA-109 66.))C ln PAl Steam Sample PAL Stcam Sample A~i~'g late)iiii]<.jig i g~~0<1D TABLE 3.6-l Continued COHTA1murr 1SOLAT10}t VALVES 68, qCN-2SO 70.R-300~J.VhLVE HlNh FNICTlOH*.';;l.:)r,'ifij~~

67.l(CR-252 Prlaar Mater to Preaaurl acr Rel I I 0 RCP Seal Mate Dlacharge g<iif , 69.qCH<<350.RCP Seal llatar Dlacl arI>><,~~I r LetdoMn to Letdoun llx,;i(..c'.;~71~QCR-301.Letdoun to Latdoun Ilx.,~~.'~72.QCk-919, Dealn Mtr.Supply for kufuellng~~,~7 3.QCR-920.Dealn lllr.Supply fnr Refuall fef'Tank Cav Cavity 10'LS g 10 C.10 PCR-<u 75, RCR-100 76.RCR-101 VCR-10 78~VCR-1 1 79.'CR-20 80.VCh"21 81" XCR-100 Xck-101 Con(aliment Service hlr'l PRE RelleF Tank l'us Anal.~~~iljA)II PRX Relief T nk to Gas hnal..Glyco'upply to Fan Cooler 1~I'~..i<Ii lycol Supply to Fan Cooler Glycol Supply f roa Fan Cooler ta,)(...'lycol Supply from Fan Cooler Control Alr to Contalnaent Control hlr tu Cuntaliwunl lao>C 10 g lo 10 g 10 g 10 g 10+10

0 4 l.CCH-45 l 2.CCH-452 3.CCH-453 4.CCH-454 CCH-458, 6~CCH-459 7.ECk-3l 8.ECk-32 9.ECR-33 10.ECN-35 I l.ECN-u., VALVE HUHBER n'I A.Pl AGE"h" lSULATlr>N pl'3.XCR<<102-.g ld 84.Xck-103 hh B.FllhBE"8" 18OLATlOH TABLE 3.6-l (Corrtlrnred

.COHTAIHHEHT IlsOLATlOH VALVES BIHCT1OH Cu>>t in>>ed I1 CCN froa RCP Oil Caolere CCM froa RCl'~Oi l Coolere CUl trara RCl'hera 1 barrier Ct:LJ froa RCl'herraal ga er CCM co NCP Oil Coo re 4 CCH to NCl'g Caalere 4, The al.barrier Thermal b rter Cantui ent Cbrit u iruaent Canto leant Airborne kad Honltar Airborne kad Honttor Airborne Red Honltor Co>>culruaent Alrburne kad Honitar Cantalnaent Airborne kad Honltor Cuntrol Alr to Co>>twlruaant laulattan g~Control hlr to Carrteintaent 1SOLATlOH TlHE Ill 8~0lD05 Q lO g lO g60 g60 g 30$60 g60 g lO g lO Q lO es Vhl.VE HlANBR n.IllhSE"a" C)ED 12'CR-901 13.MCR-903)4.MCR-905 15.MCR-907 16.MCR-909 17.MCR-911 18.MCR-913 19 o MCR-915 20'CR-921 21.MCR-923 22.MCR-92$rt 23'CR-927 O L ThRI.E 3.6-1 Continued COHThlHHEHT I S01ATIOH Vhl,VES 4 FHHCTIOH I l.~*~'I SOIATIOH Cont jnned~~HESM~to Lou.Containment Vent I 1 HBSM from~ou.Containment Vent I 1 HBSM to I.ou.Cab ainment Vent l2 HESM from I.ou.Conte'ent Vent I2 HESM to Lou.Cantainment nt l3 HESM from I.ou.Conte ment Vent~~f3 HESM to l,ov.Co tainment Vent I4 HESM from L u Contalnmcnt Vent I4 HESM o lip, Contuinment Vent I'1 lESM from Hp.Contalnmcnt Vent Il HESM to Up.to Containment Vent,l2 HESM from Up.Containment Vent l2 I'SOIATIOH TIHE IH SECOlIDS 410 4ta 410 ala 41a Xl 0~t C'>>~I%OP hl.VE}MBFR..;Th}}LE 3.6-l Contf nnci}COHThlNHRHT I SOIATIOH Vhl.VES FllHCTlOH 1SOLhTIOH TIHE IH SECOHDS}}.P}}hSE.~D" ISO}.hTIOH 24'CR-929 25'CR-93l 26'CR-933 27.MCR-935 2a.MCR-9Iil 29.MCR-942 3n.MCR-943 31.MCR-944 32.MCR-945-33~MCR-9Ii6 34.MCA-947 35'CR-948/I'ESIP frnm RCP Hator hfr Cooler}lESM from RCP Hotnr hir Cooler Cantfnned}lESM to}}p.Containment Vent$3 HESM fram}}p.Cantainment Vent l3 HESM to}}p.Containment Vent l4 HE M Erom lip.Cnntainmcnt V I4 HESM to G Hotor hir aoler HFSM to RCP}}o+ir Cooler}}ESM ta RCP--otor hik>>ooler M~c RCP Hotor hir Coole I K 8 L}1 SM from RCP}lotor hir Cooler}}ESM from RCP Hotor hir Cooler la<lo 4}a<fa 6}O 5}O go}O 36.MCR~51 3, MCR-952 3D.MCI}-953 39.MCB-954 HESM ta ACP Hotor hir Cooler Vent I 1}}ESM ta RCP}lator hir Cooler Vent l2}IESM to RCP}lotor Cooler Vent l3 HESM ta RCP Ho}or.Cooler Vent f4<}o ga .~~-~ii'l j'~'t~'et+'i<<I);ii ic~,t 4a.s'..~l i>>TABLE 3.6-'1 (Continued I~),I COHThltltlEHT I SOl.hTION Yhl.VES Vhl.VE NHHllER FllHCT ION ISOl ATIOH TINE IH SECONDS B.I 40'llhSE"9" o~42~Q'3'4, MCR-957 MCR-958 MCR-961 45.MCR-963 46.MCR-965 41.OCR-967 48~49.I 50.51.Q,52.53.54.llCR-900 OCR-902 MCR-.904 MCR-906 MCR-908 MCR-914 P 41.MCR-956 4I 0/'10<to HESM to RCP l.aver Containiient Vent l3 HESll f rom Lovor Containment Vent l3)IESM Co RCl'over Containment Vent l4 HESM from l.over Containment Vent lA.<10<)0<10 i HESM from.RCP'Motor hir Cooler Vent I 1 HESM fram RCP ttotar hir Caaler Vent l2 tlESM from RCP)totar Air Cooler Vent l3 NESM fram RCP}lotor hlr Coaler Vent l<10 NESll to Instr.Ibm'.East Vent<<0 HESM fram Instr.ltm.les Vent<10 NESM ta Instr.Rm.at Vaunt~~)0 HESM f rom Inst, Rm.Meat Vent tlESM ta C Lover Containment Vent Il~>>4'-)0 tlES~from Lover Containment Vent ll~510 HESM to ttCP Lavar Containment Vent l2<10 HESM fram Lover Containment Vent J2<10 CONTAINMEHT ISOLATION VALVES n n o O VALVE NUMBER.B,+PIIASE"B" ISOLATION 56.MCR-920 57'CR-922'a.WCR-924 59.WCR-926 60.MCR-928 61'CR-930 62'CR-932 63.MCR-934.64'CR<<960 65.MCR-962 66~MCR-964 67'CR-966 FUNCTION I~I Continued NESW NESW NESW NE NESW NESW NESM to RCP Upper Containment Vent fl I from Upper Containment Vent ill to RCP<Upper Containment Vent 82 from Upper Containment Vent d2 to RCP Upper Containment nt P3 fro Upper Containm Vent 83 to RCP Up er Co tainment Vent lt4 from Uppe on'ment Vent N4 NESW NES to I trument Room E st Vent rom Instrument Room East ent to Instrument Room Meat Vent NESW from Instrument Room West Vent ISOLATION TIME IN SECOND+10<10<10.,~10 C.CONTAINMENT PA GE AND EXHAUST**1.VCR-101 Instr.Room Purge Air Inlet p 2.VCR-102 3 VCR-103 VCR-104 K u&O'I Ag Lower Comp.Purg Outlet Instr~Room Purge hir Outlet Lower Comp.Purge hi,r Inlet

-"1~~tI)~'I,~,'" r g I~~&~v Tnf'.LE 3.6-1 (Continued) 'OHTAIHHEHT ISOLATIOH'VALVES yhLVC nuHAEA C.COHThl i>ME tlT PUAGE 6.VCA-106 7.VCA-107*0.VCA-201 9.VCA-202 10.VCA-203 11.VCA-204 12.VCA-205'I 13.VCA-206--lh.VCA-20)'F UNCT IO)l.l:.'D ENINUST Cont lnued*~Upper Comp.Purge AIr Outlet'orat'.Press.Aellef Fan lsolat n Instr, oom Purge Air Inle InStr.AOOA>Pa>rge h l Outlet Lower Comp.Pu..e Alr Inlet lower Comp.Purge lLlr utlet Upp-Comp.Purge Air Outlet plier Cooqi.Purge h I r Outlet Coot.Press Acllef Fan Isolation: I SOLATJ T1HE IHWECONOS c 5 c 5 5 c 5'c 5 5 c 5 5 c 5 D.HAIHIAL I SOI.AT ION VALVES l.)Ol-1 1 1 r 2, lcl..29 AllA to AC Cold l.egs"AllA Inlet to Piuops'.Iln ,~~I~$"~ 4 n C)o 7C E.10.1CH-321k OTIIEA 1.CS-442-1 2.CS-442-2 3.CS-4-3 4.S-442-4 VAI.VE NUHBEA HAHUAL ISOLATION 3." 1CH-250 4.1CH-251 5.1CH-260 6.1CH-265 7.1CH-305 8.1CH-306 9.1CH-311rIr TABLE 3.6-1 (Continued) CONTAINHEHT ISOLATION VALVES~FUNCTION ALVES (Continued) (1)~~Boron Injection Inlet oron In)ection Inlet Safe y In)ection Inlet Safety In ection Inl e p'I RIIA Suction Fro.ump/AIIA Suctio.-rom Sum RIIA t-AC Ilot Legs I I A to AC Ilot Legs-~Seal Wtr.to RCP 81 Seal Wtr.to RCP 02 Seal Wtr.to ACP E3 Seal Wtr.to ACP N4 ISOLATI TIME)IH CON OS HA flA NA NA NA /I//THZS PAG" ZNTENTZONALLY BLANK/"~X~~~I'~'~4~~////./~~~D.C COOK-UNIT 2 3/4 6-2B Amendment No.81 d~ TABLE 3.6-1 (Continued) CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME IN SECONDS E.OTIIER (Continued) 5.SI-189 6.PA-342 7~NPZ-151 VI 0.N-160 9.SM-1 10.N-102 11.SI-171 12'I-172 13.SI-194 14'W-275 15.CS-321 NA NA NA NA NA NA NA NA NA C.Relief Valve Vent llole Serai e Air to Containment NA Dead Wei t'a1ibrator N2 to R.C.'ain Tank Air Particle/Rad Gas Detec Return N2 To Accumulators Safety Infection Tes Lib Safety Infection est Line Safety Ingec ion Test Line Primaryp r.to Pre.Relief Tank R.C.S4 Charging L I ~~TABLE 3.6-1 (Continued) CONTAINHENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME IN SECONDS 22~24.25~i E.OTIIER (Continued) '~~16.SF-152.-'.,Refueling Wtr.to Refuel Cavity~el.p 17.SP-154 Refueling Wtr.'.to Refuel Cavity 18'F-159 Refuel'ing Cavity Drain'9'F>>160 Refueling<Gavity Drain 20, N-159 N to Prz.Reli,ef Tank 21'CM-135 CCM to ReactoriSupports CA-181-N Meld Channel'Supp~le'ir 23'A-181-8 Meld Channel S+ply Air~~*SM-8 Upper Cont;Grab Sample*SM-10 Upper nt.Grab Sample/NA NA NA NA NA NA NA I~~i~~l.i~~.~.i~~'I'i' TABLE 3.6-1 (Continued) CONTAINMENT ISOLATION VALVES VALVE NUHBER FUNCTION ISOLATION TINE ZN SECONDS E.OTNER (Continued) 26.PPP-300 27.PPP-301 28.PPP-302 29.PPP-303 30.PPA-310 and PPA-311 31.-PPA-312 and PPA-313 32.Blind Flange 33.Blind Flange 34.Blind Flange 35.Blind-Flange Instrument Penetration Instrument Penetration Instrument 0 netration Instrument Penetration I I y'Instrument Penetration -,'!Instrument Penetra ion 4 Fuel Transfer+etration Ice Condemn)fr.Ice Supply Ice C~odenser Ice Return InMore Flux Thimble Access NA NA NA NA 0 J~ ~g 'TABLE 3.6-1 (Continued) n C)C3 TABLE NOTATlOH L.COtiTAI tlHCNT 1SOLATI ON VALVES.Hay be opened on an intermittent basis, under administrative control.~~t(ot subject to Type"0" or"C" Leak Tests.tiA Check valves, blind flanges on normally closed valves which do not receive containment isolation signals;isolation time not applicable.'1) includes motor operated valves.which do not isolate~automatically.

Contairxaent purge supply and exhaust isolation gvlves (VCR-101 through 106 and VCR-201 through 206)ioay bo opened under Techn,ical Specif/cation 3/4,6.1.7.
L. CONTAINMENT'YSTENF BASES 3/4.6.2 5EPRESSURIZATIOH AND COOLING SYSTEMS 3/4.6.2.1 COHTAIHMEHT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that contain-.ment depressurization and cooling capability will be available in the event of a LOCA.The pressure reduction and resultant lower containment. leakage rate are consistent with the assumptions used fn the accident a na lys es.3 4.6.2.2 SPRAY ADDITIYE SYSTEM The OPERABILITY of the spray additive system ensures that sufficient HaOH is added.o the containment spray in the.event of a LOCA.Thc limits on HaOH volume and concentration ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA.This pH band minimjzes the evolution of iodine and mfnfmizes thc effect of.chloride and caustic stress corrosion on mechanical systems.and components. These assumptions are consistent with the iodine removal efBcfcncy assumed in.the accident analyses.The contained water volume limit includes an allowance for water not usable because of tank discharge location or other physfcal'haracteristics .3/4.6.3 CONTAINMEHT ISOLATION YALYES Thc OPERABILITY of the containment.isolation valves erisures that the containment atmosphere will be isolated from the-outside environm'ent in the event of a release of radioactive material to the containment atmos-.phere or pressurization of the containment. Containment is4latfon within the time limits specified ensures that the release of radioactive matcrfal to the environment will-be consistent with the assumptions used fn the analyses for a LOCA.0.C.COOK-UNIT 2 B 3/4 6-3 Anendment Ho.~ Insert A: The opening of containment purge and exhaust valves and locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations: (1)stationing a qualified individual, who is in constant communication with control room, at the valve controls, (2)instructing this individual to close these valves in an accident situation, and (3)assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment. ~~ Attachment 3 to AEP:NRC:1178 Proposed Technical Specifications Pages t DEFINITIONS REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.CONTA NMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when: 1.8.1 All penetrations required to be closed during accident conditions are either: a.Capable of being closed by an OPERABLE containment automatic isolation valve system, or b.Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.1.1.8.2 All equipment hatches are closed and sealed.1.8.3 Each air lock is in compliance with the requirements of Specification 3.6.1.3.1.8.4 The containment leakage rates are within the limits of Specification 3.6.1.2 CHANNE CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. CHANNEL CHEC 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. COOK NUCLEAR PLANT-UNIT 1 1-2 AMENDMENT NO.~440-3 4 6 CONTAINMENT SYSTEMS 3 4 6 PRIMARY CONTAINMENT CON AINMENT INTEGRITY-LIM TING CONDITION FOR OPERATIO 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained. APPLICABILITY: MODES 1, 2, 3 and 4.ACTION: Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.SURVEILLANCE RE UIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated: a.At least once per 31 days by verifying that: 1.All penetrations* not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.1, and 2.All equipment hatches are closed and sealed.b.By verifying that each containment air lock is in compliance with the requirements of Specification 3.6'.3~*Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position.These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.COOK NUCLEAR PLANT-UNIT 1 3/4 6-1 AMENDMENT~4444 CONTAINMENT SYSTEMS 3 4 6 3 CONTAINMENT ISOLATION VALVE LIMITING CONDITION FOR OPERATION 3.6.3.1 Each containment isolation valve shall be OPERABLE.Containment purge valves and locked or sealed closed valves may be opened on an intermittent basis under administrative control.The ACTION statement of T/S 3/4.6.3.1 is not applicable to the containment purge supply and exhaust isolation valves.The Limiting Condition for Operation and its associated ACTION statement for these valves is given in Technical Specification 3/4.6.1.7. ACTION'ith one or more of the containment isolation valve(s)inoperable, either: a.Restore the inoperable valve(s)to OPERABLE status within 4 hours, or b.Isolate each affected penetration within 4 hours by use of at least one deactivated automatic valve secured in the isolation position, or c.Isolate each affected penetration within 4 hours by use of at least one closed manual valve or blind flange, or d.Be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.The provisions of Specification 3.0.4 are not applicable. SURVEILLANCE RE UIREMENTS 4.6.3.1.1 Each containment isolation valve shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.COOK NUCLEAR'PLANT -UNIT 1 3/4 6-14 AMENDMENT NO.QS CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.6.3.1.2 Each containment isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by: a.Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.b.Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.c.Verifying that on a Containment Purge and Exhaust isolation signal, each Purge and Exhaust valve actuates to its isolation position.4.6.3.1.3 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.COOK NUCLEAR PLANT-UNIT 1 3/4 6-15 AMENDMENT NO.407-, 444~i4-Pages 3/4 6-17 through 3/4 6-22 deleted COOK NUCLEAR PLANT-Unit 1 3/4 6-16 AMENDMENT NO.O5-4 I CONTA NMENT SYSTEMS BASES 3 4 6 2 DEPRESSURIZATION AND COOLING SYSTEMS 3 4 6 2 1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA.The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.3 4 6 2 2 SPRAY ADDITIVE SYST The OPERABILITY of the spray additive system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA.The limits on NaOH minimum volume and concentration, ensure that 1)the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2)corrosion effects on components within containment are minimized. These assumptions are consistent with the iodine removal efficiency assumed in the accident analyses.3 4 6 3 CONTAINMENT ISOLATION V LVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.The opening of containment purge and exhaust valves and locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations: (1)stationing a qualified individual, who is in constant communication with control room, at the valve controls, (2)instructing this individual to close these valves in an accident situation, and (3)assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment. 3 4 6 4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. Either recombiner unit is capable of controlling the expected hydrogen generation associated with 1)zirconium-water reactions, 2)radiolytic decomposition of water and 3)corrosion of metals within containment. COOK NUCLEAR PLANT-UNIT 1 B 3/4 6-3 DEFINITIONS REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when: 1.8.1 All penetrations required to be closed during accident conditions are either: a.Capable of being closed by an OPERABLE containment automatic isolation valve system, or b.Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.1.1.8.2 All equipment hatches are closed and sealed, 1.8.3 Each air lock is in compliance with the requirements of Specification 3.6.1.3, 1.8.4 The containment leakage rates are within the limits of Specification 3.6.1.2, and 1.8.5 The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings)is OPERABLE.CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same paiameter. COOK NUCLEAR PLANT-UNIT 2 1-2 AMENDMENT NO.~
3 4 6 CONTAINMENT SYSTEMS 3 4 6 1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY IMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained. APPLICABILITY: MODES 1, 2, 3 and 4.~CT~O Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.SU VEILLANCE E UIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated: a.At least once per 31 days by verifying that: l.All penetrations* not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.1, and 2.All equipment hatches are closed and sealed.b.By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.*Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position.These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.COOK NUCLEAR PLANT-UNIT 2 3/4 6-1 AMENDMENT~ CONTAINMENT SYSTEMS 3 4 6 3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 Each containment isolation valve shall be OPERABLE.Containment purge valves and locked or sealed closed valves may be opened on an intermittent basis under administrative control.The ACTION statement of Technical Specification 3/4.6.3.1 is not applicable to the containment purge and exhaust isolation valves.The Limiting Condition for Operation and its associated ACTION statement for these valves are given in Technical Specification 3/4.6.1.7. APPLICABILITY: MODES 1,2,3 and 4.ACTION pith one or more of the containment isolation valve(s>inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either: a.Restore the inoperable valve(s)to OPERABLE status within 4 hours, or b.Isolate each affected penetration within 4 hours by use of at least one deactivated automatic valve secured in the isolation position, or c.Isolate each affected penetration within 4 hours by use of at least one closed manual valve or blind flange;or d.Be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.The provisions of-Specifications 3.0.4 are not applicable. SURVEILLANCE RE UIREMENTS 4.6.3.1.1 Each containment isolation valve shall be demonstrated OPERABLE prior I to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.COOK NUCLEAR PLANT-UNIT 2 3/4 6-13 AMENDMENT NO.~ 1 CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.6.3.1.2 Each containment isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by;a.b.C.Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.Verifying that on a Containment Purge and Exhaust isolation signal, each Purge and Exhaust valve actuates to its isolation position.4.6.3.1.3 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5 COOK NUCLEAR PLANT-UNIT 2 3/4 6-14 AMENDMENT NO. Page 3/4 6-16 through 3/4 6-32 deleted COOK NUCLEAR PLANT-Unit 2 3/4 6-15 AMENDMENT NO. e o~g~ CONTAINMENT SYSTEMS BASES 3 4 6 2 DEPRESSURIZATION AND COOLING SYSTEMS 3 4 6 2 1 CONTAINMEN SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA.The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.3 4 6 2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the spray additive system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA.The limits on NaOH volume and concentration ensure a pH value of between 8.5 and 11.0'or the solution recirculated within containment after a LOCA.This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. These assumptions are consistent with the iodine removal efficiency assumed, in the accident analyses.The contained water volume limit includes an allowance for water not usable because of tank discharge location or other physical characteristics. 3 4 6 3 CONTAINMENT ISOLA ION VALVES The OPERABILITY of the containment.isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.The opening of containment purge and exhaust valves and locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations; (1)stationing a qualified individual, who is in constant communication with control room, at the valve controls, (2)instructing this individual to close these valves in an accident situation, and (3)assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment. COOK NUCLEAR PLANT-UNIT 2 B 3/4 6-3 AMENDMENT NO~ ~IA Attachment 1 to AEP:NRC:1143 10 CFR 50.92 Analysis for Changes to The Donald C.Cook Nuclear Plant Units 1 and 2 Technical Specifications Mt Attachment 1 to AEP:NRC:1143 Page 1 1.0 Sections to be Chan ed A.Unit 1 1.2.3~4~5~6.7~8.9.10.T/S 3/4.7.8-page 3/4.7-28 T/S 3/4.7.8.a-page 3/4.7-28 T/S 3/4.7.8.b-page 3/4.7-29 T/S 3/4.7.8.c-page 3/4.7-29 T/S 3/4.7.8 e-page 3/4.7-30 T/S Table 3.7-4-pages 3/4.7-31 through-40a T/S 3/4.7.8 Bases-page B 3/4.7-6 T/S 6.10.2.n Administrative Control-page 6-20 T/S 3/4.7.9-3/4.7.10;pages 3/4.7-41 through-52 T/S Index-page IX B.Unit, 2 1.2.3~4~5.6.7~8.9~10.T/S 3/4.7.7-page 3/4.7-20 T/S 3/4.7.7.1.a -page 3/4.7-20 T/S 3/4.7.7.1.b -page 3/4.7-21 T/S 3/4.7.7.1.c -page 3/4.7-21 T/S 3/4.7.7.1.e -page 3/4.7-22 T/S Table 3.7.9-page 3/4.7-23 through-33 T/S 3/4.7.7 Bases-page B 3/4.7-5 and-6 T/S 6.10.2.n Administrative Control-page 6-20" T/S 3/4.'7.9- 3/4."7.10'- pages'3/4.'7-27 through-40 T/S Index-page IX 2.0 Extent of Chan e This license amendment request proposes to revise Technical Specifications (T/Ss)3/4.7.8 and 3/4.7.7 for Units 1 and 2, respectively, and their associated bases to be consistent with the guidance provided in NRC Generic Letters 84-13 and 90-09.The changes to the T/Ss include replacing the current T/S requirements for snubber visual inspection intervals with the alternative requirements for snubber visual inspection intervals that are provided in NRC Generic Letter'90-09.Also,'he'snubber component list tables associated with the T/Ss mentioned above will be removed based on the guidance set forth in NRC Generic Letter 84-13.3.0 S ecific Chan es Re ested (The change numbers in the following discussion refer to those in Section 1.0, above.)We propose to modify the LCO in both units to say,"All safety-related snubbers shall be operable." ~P 4~i yp~q,N a't~ps a-,pip, eel r Attachment 1 to AEP:NRC:1143 Page 2 2.A new paragraph is being proposed to replace T/Ss 3.7.8.and 3.7.7.1"Visual Inspections," for Units 1 and 2, respectively, as recommended by Generic Letter 90-09.Generic Letter 90-09 discusses the use of Table 3.7.4 and Table 3.7.9 in determining inspection intervals, inspection of groups independently from each other, and commencement of the start of the first, inspection interval.Unit 1 T/S 4.7.8.a and'Unit 2 T/S 4.7.7.1.a currently read as follows: a.Visual Ins ections The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of commencing POWER OPERATION and shall include all snubbers listed in Table 3.7-4.If less than two (2)snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months plus or minus 25%from the date of the first inspection. Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule: No.Inoperable Snubbers er Ins ection Period Subsequent Visual Ins ection Period*0 1 2 3,4 5,6,7 8 or more'18 months plus or minus 25%12 months plus or minus 25%6 months plus or minus 25%124 days plus or minus 25%62 days plus or minus 25%31 days plus or minus 25%The snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor operation. Each group may be inspected independently in accordance with the above schedule.*The inspection interval shall not be lengthened more than one step at a time.The provisions of Specification 4.0.2 are not applicable. ggThe visual inspection of inaccessible snubbers may be delayed until the end of the.Cycle 11 refueling outage.We are proposing to modify these T/Ss to read as follows: a.Visual Ins ections Snubbers are categorized as inaccessible or accessible during reactor operation. Each of N-Cg'l (l Se~, hc we Attachment 1 to AEP:NRC:1143 Page 3 these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 3.7-4.The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 3.7-4 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment No.3.This section is being revised to incorporate the wording provided in Generic Letter 90-09.Currently, Unit 1 T/S 4.7.8.b and Unit 2 T/S 4.7.7.1.b read as follows: b.Visual Ins ection Acce tance Criteria Visual inspections shall verify (1)that there are no visible indications of damage or impaired OPERABILITY, (2)attachments to the foundation or supporting structure are secure, and (3)in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next.visual inspection interval, providing that (1)the cause of the re)ection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2)the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.8.d (Unit 1)or 4.7.7.1.d (Unit 2)as applicable. However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.We are proposing to modify these T/Ss to read as follows: b.Visual Ins ection Acce tance Criteria Visual inspections shall verify (1)that there are no visible indications of damage or impaired A 4'Il II 4, 4'v~ly A'a Ht't~'~"4 Ai v~4 4 H 1 NI.Iy 4~4~.ll'Ay,y I ly A I gQ 44 Attachment 1 to AEP:NRC:1143 Page 4 OPERABILITY, (2)attachments to the foundation or supporting structure are secure, and (3)in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified as acceptable for the purpose of establishing the next visual inspection interval, providing that (1)the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2)the affected snubber is functionally tested in the as found condition and determined OPERABLE per.Specification 4.7.8.1.d (Unit 1)or 4.7.7.l.d (Unit 2)as applicable. All snubbers found connected to an inoperable common hydraulic fluid reservoir shall be counted as unacceptable for determining the next inspection interval.A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber.If continued operation cannot be justified, the snubber shall be declared inoperable.and the ACTION requirements shall be met.4, 5.We are proposing to modify the surveillance to remove the reference to Tables 3.7-4 and 3.7-9,"Safety Related Hydraulic Snubber," in Units 1 and 2, respectively. 6.We are proposing to add Tables 3.7-4 and 3.7-9,"Snubber Visual Inspection Interval," in Units 1 and 2, respectively. These tables provide limits for determining the next inspection interval.Footnotes to Tables 3.7-4 and 3.7-9 provide further guidance on interpolation, determining inspection intervals, and the, applicability.of T/S 4.0.2 (extending surveillance intervals) 'consistent with the guidance provided in Generic Letter 90-09.7~We are proposing to modify Bases Sections 3/4.7.8 and 3/4.7.7, in Units 1 and 2, respectively. Paragraphs are being inserted to explain the visual inspection interval and the acceptance criteria described in Generic Letter 90-09 and the control being placed on the snubber component list that is proposed to be removed from the T/S.The second paragraph of the bases for Unit 1 T/S 4.7.8 and Unit 2 T/S 4.7.7.1, currently reads as follows! fl~~k+'f t p~~t W~1 s t x lf f1'l v t<'~.5~a 4 S 8,~+A k ly)'f I f'j+$U V f P'1 l't, I V h L k I II, II s 1 Attachment 1 to AEP:NRC:1143 Page 5 The visual-inspection frequency is based upon maintaining a constant level of snubber protection to systems.Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%)may not be used to lengthen the required inspection interval.Any inspection whose results required a shorter inspection interval will override the previous schedule.This paragraph is being revised to read as followss The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.The method for determining the next interval for the visual inspection of snubbers is provided based upon the number of unacceptable snubbers found during the previous inspection, the category size for each snubber type, and the previous inspection interval per NRC Generic Letter 90-09.A snubber is considered unacceptable if it fails to satisfy the acceptance criteria..of the visual inspection. Any inspection whose results-required-a shorter inspection interval ,*will override the previous schedule.Additionally, the following paragraph is being added to the bases for both units: A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c)of 10 CFR Part 50.The accessibility of each snubber shall be determined and approved by the Plant Nuclear Safety Review Committee. The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and recommendations of Regulatory Guides 8.8 and 8.10.The addition or deletion of any snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.8.We are proposing to remove the reference to Tables 3.7-4 and 3.7-9 in Units 1 and 2, respectively. ~~~"ICOV 14 1 ll g 8 J~jg 49 Attachment 1 to AEP:NRC:1143 Page 6=9,10.We are proposing to'renumber the pages in-T/S Sections 3/4.7.9 and 3/4.7.10 for both units as a result of removing the snubber component tables.The T/S index will also be revised to reflect the page number changes.4.0 Discussion S stem Descri tion and Safet Function Snubbers ensure that the structural integrity of the reactor coolant system and other safety-related systems is maintained during and following a dynamic event.Snubbers, or dynamic restraints, are used to restrain piping or equipment during dynamic events or transient loads while allowing relatively unrestrained movement of the piping/component during normal heatup or cooldown operations. The Technical Specifications (T/S 4.7.8c and T/S 4.7.7.1c for Units 1 and 2, respectively) that typically involve removing the snubber and testing it on a specially-designed test stand impose surveillance requirements for visual inspection and functional testing of safety-related snubbers.The NRC defines"visual inspection" in Generic Letter 90-09 as the observation of the condition of the installed snubbers to identify those that are damaged, degraded, or inoperable as caused by physical means,.leakage, corrosion, ,or.environmental exposure, which typically involves removing the"snubber and testing it on a specially-designed test stand.In this manner the structural integrity of safety-related equipment is maintained. Functional testingf which typically involves removing the snubber and testing it on a specially-designed test stand, provides a high confidence level that'he snubbers will operate within the specified acceptance limits.In this manner the structural integrity of safety-related equipment is maintained. The performance of visual examinations is a separate process that complements the functional testing program in ensuring snubber operability. The current T/Ss specify a schedule for snubber visual inspection that is based on the number of inoperable snubbers found during the previous visual inspection. Consequently, irrespective of the size of the snubber population or group the visual inspection schedule can be excessively restrictive, requiring inspections as frequently as once every 31 days.This has resulted in plant personnel being subjected to unnecessary radiological exposure to comply with the visual examination requirements. To alleviate this situation, the NRC staff developed an alternate schedule for visual inspections. In Generic Letter 90-09, the NRC staff states that this alternate schedule establishes an acceptable visual inspection confidence for snubber operability for nuclear power stations.Furthermore, this alternate schedule generally 't I jl'~41@I>I e.1~,-kA 4N Attachment 1 to AEP:NRC:1143 Page 7"allows for the'performance of visual inspections and corrective actions during plant outages, which should reduce associated potential radiological exposures. The NRC staff, in Generic Letter 84-13,"Technical Specification for Snubbers," reassessed the inclusion of snubber listings within the T/Ss.'he generic letter:concluded"that such listings are not necessary, provided the snubber T/S is modified to specify which snubbers are required-to.be operable.The proposed change incorporates into Cook Nuclear Plant T/S wording from Generic Letter 84-13 and removes the snubber list contained in Tables 3.7-4 and 3.7-9, Units 1 and 2, respectively. This snubber list will now be contained in a Cook Nuclear Plant procedure. The population of snubbers that will be included in the proposed administrative procedure will be those listed in the current T/S tables.Justification Periodic visual inspection of snubbers complements the existing functional testing program, and provides additional confidence in the snubbers'perability. The existing T/S surveillance schedule is based on the number of inoperable snubbers found during the previous inspection. Since Cook Nuclear Plant's existing schedule for snubber visual inspection is based solely on the number of inoperable snubbers found during the previous visual inspection, irrespective of the size of the, snubber population or group, the" visual'nspection -'schedule-can be excessively restrictive.. Consequently, plant personnel may be subjected to unnecessary radiological exposure in order to comply with the visual examination requirements. 'The'proposed change to the T/Ss alleviates this situation by incorporating the alternative inspection schedule provided by the NRC in Generic Letter 90-09, dated December 11, 1990.The alternative inspection schedule is based on the number of unacceptable snubbers found during the previous inspection in proportion to the size of the various snubber populations and may be as long as 48 months with good overall visual.,inspection results.As determined by the NRC, the alternate schedule for visual inspections maintains the same confidence level in snubber operability as the existing schedule.Furthermore, the NRC determined that since this line item T/S improvement will reduce future occupational radiation exposure, and since it is highly cost effective, the alternate inspection schedule proposed in Generic Letter 90-09 is consistent with the NRC's policy statement on T/S improvement. The NRC, in Generic Letter 84-13,"Technical Specification for Snubbers," reassessed the inclusion of snubber listings within the T/Ss.The letter concluded that such listings are not necessary, provided the snubber T/S is modified to specify which snubbers are I I+It'~<<i:il/>>'I t II I i'f'*'I'f t+S 4 t>>~>>la I I>><<II I>>I I\tl>>I~~>>, Attachment 1 to AEP:NRC:1143 Page 8 required to be operable.'he generic letter noted that this modification did not alter the T/S requirements for record keeping or the need for 10 CFR 50.59 evaluations for changes in snubber=-quantities, types, or location.The changes that we are proposing to make to the Cook Nuclear Plant's T/Ss are consistent with the guidance provided in Generic Letter 84-13.'5.0 No Si nificant Hazards Determination We have evaluated the proposed T/S changes and have determined that the changes should involve no significant hazards consideration based on the criteria established in 10CFR 50.92(c).Operation of the Cook Nuclear Plant in accordance with the proposed amendment will not: (1)Involve a si nificant increase in the robabilit or.-.conse ences of an accident reviousl evaluated. The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed changes do not result in any physical change to the facility which could cause an increase in the probability or consequences of any previously evaluated accident.The requested changes incorporate the alternative inspection schedule provided by the NRC in Generic Letter 90-09, dated December 11, 1990, and remove the snubber..component lists, from, the T/Ss,in accordance with the guidance set forth in'eneric Letter'84-13, dated May 3, 1984 As determined by the NRC, the alternative schedule for visual inspections maintains the same confidence level as the'existing schedule and, therefore, does not affect the probability or consequences of an accident previously evaluated. The removal of the snubber component lists from the T/S will not alter the existing T/S requirements nor change the-.components to.which they apply.The.lists, being removed from.the T/Ss will be placed under administrative control and a 10 CFR 50.59 evaluation will be required for changes in snubber quantities, types, or location.The editorial changes to the T/S will not affect the probability or consequences of an accident in any way, they merely reflect the shifting of page numbers.Therefore, the proposed amendment does not involve a change in the probability or consequences of an accident previously evaluated. (2)Create the ossibilit of a new or different kind of accident from an reviousl anal zed..The proposed amendment does not create the possibility of a jj<<, I, h I.~4 f<<%~~>fl'S lh-40 S+yy hg<4ll<<+4),i>4>>'I 4.~j~~<<4<<4hal'<<e 4<<'-<<M~<<~~4<<I<<4 Attachment 1 to AEP:NRC:1143 Page 9 new or different"kind of accident previously evaluated. The,.proposed amendment does not result in any physical change to the plant or method of operating the plant from that allowed by the T/Ss.No new failure modes have been defined for any system or component nor has any new limiting single failure been identified. The NRC has generically reviewed the proposed changes and has determined that the alternative snubber visual inspection interval maintains the same confidence level in snubber operability. Therefore, the proposed change does not create the possibility of a new or different kind of accident.The removal of snubber component lists will not alter existing T/Ss requirements or those components to which they~apply.No physical changes are being made to the facility as a result or in support of the removal of the component lists.Since the requirements for the components will remain the same, this proposed amendment will not affect the outcome of previously evaluated accidents. A 10 CFR 50.59 review will be performed for changes to the administrative snubber list to ensure that an unreviewed safety question, such as a new accident, does not result from future changes in the list.The editorial changes to the T/Ss will not affect the previously evaluated accidents since they do not change the-meaning of any T/Ss..Therefore, the proposed amendment does not create the possibility of a'new or different kind of accident from any previously evaluated. (3)Involve a si nificant reduction in a mar in of safet The proposed amendment does not involve a significant reduction in the margin of safety.As stated above, the proposed amendment incorporates the alternative T/S requirements for visual inspections of snubbers provided by the NRC in Generic Letter 90-09 and removes the snubber component lists from the T/Ss in accordance with the guidance set forth in Generic Letter 84-13.The NRC has previously reviewed these changes and determined that the alternative visual inspection interval maintains the same confidence level in snubber operability. The removal of the component lists from the T/Ss will not alter the existing T/S requirements nor change the components to which they apply.The component lists will be incorporated into plant procedures that are sub)ect to the change control provisions for plant procedures specified in the administrative controls section of the T/S.Since neither the list of components nor the requirements that those components are required to meet are changing, the margin of safety is not affected. l e$tV.)i%$g t.W'I~'e>O.'ik'i-<>>ss>+sW r~%<a>si-a'! ws>qseg W~'I Attachment 1 to AEP:NRC:1143 Page 10 The editorial changes-made.to refine the T/Ss will not affect the margin of safety.Consequently, the proposed amendmentg including both changes, does not involve a significant reduction in the margin of safety.'6.0 Pendin T Ss Pro osals Im actin'This Submittal Changes to page B 3/4 7-5 were also submitted in AEPsNRC:0398R, dated June 29, 1989, and AEP:NRC:0398U, dated September 10, 1990.The changes proposed in this letter are in addition to those changes and do not supersede them.Our letter AEP:NRC:0692CC dated February 14, 1992 contains<<->'"<<'proposed>> changes to pages that.are.also contained in this submittal. However, the pages affected are included in this submittal only due to repagination; no actual T/Ss are impacted.
Attachment 2 to AEP:NRC:1143 Existing Technical Specifications Pages Marked to Reflect Proposed Changes v e%~41~l I 0 INDEX LIMITING CONDITIONS FOR OPERATION ANO SURVEILLANCE Rf UIREMENTS 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTE%A.C.Distribution -Operating...........................,. A.C.Distribution -Shutdown............................... 0.C.Distribution -Operating............................. D.C.Distribution -Shutdown.............................. D.C.Distribution -Operating-Train N Battery System.... 3/4.8.3 ALTERNATIVE A.C.POWER SOURCES.... ""................... " 3 4.8.9 REF VELING OPERATIONS SECTION 3 4.7 PIANT SYSTEMS (Continued) 3/4.7.9 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System................... ".".....Spray and/or Sprinkler Systems.........;..'.....--.-"."... Low Pressure C02 Systemso~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~H alon System............................................... Hose Stations~~~~~~~~~~~~~~~~~~~~~~~~~~e~~~~~i~~~~~~~~F 3/4.7.10 FIRE RATED ASSEMBLIES....................... 3 4.8 ELfCTRICAL POWER SYSTEMS 3/4.8.1, A.C.SOURCES 0 pelating~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~'~~~~~~S r hutdown o~~~~~~~~~~~~~~~~~~~~~~o~~~~~~~~~~~~~~~~cj~~~~~~~~~~PAGE 3/4 7-N'3 3/4 7-4434 3/4 7-m4>3/4 7-4$0>3/4 7-ra 0~3/4 7-$f~3/4 8-1 3/4 8-9 l 3/4 8 1Q 3/4 8-11 3/4 8-12 3/4 8-16 3/4 8-Z7 3/4 8-2Q'3/4.9.1 3/4.9.2 3/4.9.3 3/4.9.4 3/4.9.5 BORON CONCENTRATION..'..........................~...,......, 3/4 9-1 INSTRUMENTATION.............................,. ~...,.....,.. 3/4 9-2 CONTAINMENT BUILDING PENETRATIONS"~.""~" r COl+iUNI CATIONS~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~............... 3/4 9-4............... 3/4 9-5 J D ECAY TINE.~~.~.~..~..~.......~............... ~~~~..~~~~,., 3/4 9-3 D.C.COOK-UNIT1 IX Amendment No.23 iNl>25 YS 4 8 BB TI G C IO FO OPERATION sogc+y-c KKa c 3.7.8./All snubbers shall be OPERABLE.APPLICABILITY: MODES 1, 2, 3 and 4.(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).A~CTIO With one or more snubbers inoperable, within 72 hours replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.8".'5 on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.S VEILLANCE RE UIREMENTS 4.7.8.fEach snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.a.Visual Ins ec ons The irst i service v sual in ection o snubber shall b per-fo ed aft r four mo ths but ithin 10 months o commenc ng POWER 0 ERATIO and shal include all snubb rs list in Tabl 3.7-4.I ess th two (2)nubbers are foun inopera e durin the first inserv ce visual inspect n, the s cond ins rvice vis al inspec on shal be perfo ed 12 m nths plus or minus 25$from he date o the fir inspect n.Ot rwise, s sequent isual in ections s all be pe formed in accorda e with t e follow g schedu No.operabl Snubber e Ins ec o Perio Subsequ t Visual Ins ect o Period¹¹0 1 2 3,4 5,6 8 more 18 months plus 12 month plus 6 mon s plus 124 d s plus 62 ys plus 31 ays plu or nus 25%or inus'5%o minus 25 minus 2 or minus or minus 5%The s ubbers m be categ rized into two grou: Those ccessi e and hose ina essible ring react r operat on.Each roup m be in ected in ependently in accorda ce with e above hedule*The inspec on int rva s not e length ned mor than one step at t e.e pro sions f Speci cation.0.2 ar not app icable.The v ual in ection f inacce sible s bbers y be del ed until the end of t e C cle 1 refu out e.COOK NUCLEAR PLANT-UNIT 1 3/4 7-28 AMENDMENT NO.404, 444, 444, 149 EQ'l/8+~u>Il>S L-Z-=-1 1-=.aII-e5~I g, 1)I jj.~lI'il ji lj ll 11 I I I 1 I~=n a I Y" ii fj ll Ij I I I j, Il I'g-~4r'I II I'I'.I I J':j~.W~~II 11 Insert A (Page 3/4 7-28)Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 3.7-4.The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 3.7-4 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment No.
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued b.Visual Ins ection Acce tance Criteria sk~)l~@ac'GM~~c~Visual inspections shall verify (1)that there are no visible indications of damage or impaired OPERABILITY, (2)attachments to the foundation or supporting structure are secure, and (3)in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.Snubbers which appear inoperable as a result of visua nspect ons for the purpose of establishing the next visual inspection interval, providing that (1)the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2)the affected snubber is functionally tested in the as found condition and determined ing-fo~Ae-puepe stabiiehka~e-ne~wual Mepeet~~~m~ All snubber orriected to an inoperable common hydraulic fluid reservoir shall be counted as Functional Tests X~sa&l g At least once per 24 months during shutdown, a representative sample (14%)of the total of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test.For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.8CcL an additional 10%of that type of Snubber'shall be functionally tested.The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.At least 25%of the snubbers in the representative sample shall include snubbers from the'ollowing three categories: 1.The first snubber away from each reactor vessel nozzle 2.Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc.)3.Snubbers within 10 feet of the discharge from a safety relief valve b4o 4cL~SnubbersVidentified as"Especially Difficult to Remove" or in"High Radiation Zones During Shutdown" shall also be included in the representative sample.**Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.COOK NUCLEAR PLANT-UNIT 1 3/4 7-29 AMENDMENT NO.+Q4, 116 ~: E le~~e i~C~4 e~~~e~y e~.'J~~~~.K E E~~~-~.~ Insert B (Page 3/4 7-29)unacceptable for determining the next inspection interval.A review and evaluation shall be performed"and documented to)ustify continued operation with an unacceptable snubber.If continued operation cannot be justified/ the snubber shall be declared inoperable and the ACTION recpxirements shall be met. tW~4 PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position)and the spare snubber shall be retested.Test results of these snubbers may not be included for the re-sampling. If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design efficiency all snubbers of the same design subject to the same defect shall be functionally tested.This testing requirement shall be independent of the requirements stated above the snubbers not meeting the functional test acceptance criteria.For the snubber(s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber(s). The purpose of this engineering evaluation shall be to determine if the components supported by the snubber(s) were adversely affected by the inoperability of the snubber(s) in order to ensure that the supported component remains.capable of meeting the designed service.H draulic Snubbers Functional Test Acce tance Criteria The hydraulic snubber functional test shall verify that: 1.Activation (restraining action)is achieved within the specified range of velocity or acceleration in both tension and compression. 2.Snubber bleed, or release rate, where required, is within the specified range in compression or tension.For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.e.Snubber Service Life Monitorin A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be main-tained as required by Specification 6.10.2.Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for shall be reviewed to verify that the g(~<q<q<g~indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.If the indi-cated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled"service life review.This reevaluation, replacement or reconditioning shall be indicated in the records.COOK NUCLEAR PLANT-UNIT 1 3/4 7-30 AMENDMENT NO.104 \t~a4o'>a:: 1P~X A-*.:-f I~*W~p 4 II'I I f g l u~g~o.id NUMBER OF UNACCEPTABLE SNUBBERS Population Co umn o umn B Co umn C or Category Extend Interval Repeat Interval Reduce Interval Notes 1 and 2 Notes 3 and 6 Notes 4 and 6 Notes 5 and 6 80 0.100 150 200 13 300 12 25 400 18 36 500 12 48 750 20 40 78 1000 or greater 29 56 109 Note 1: Note 2: Note 3: Note 4: The next visual inspection interval for a snubber population or cate-gory size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval.Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible. These categor-ies may be examined separately or jointly.However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.Interpolation between population or category sizes and the number of unacceptable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubbers as determined by inter-polation on.If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.If the number of unacceptable snubbers is equal to or less than the number in Column B but greater that the number in Column A, the next inspection interval shall be the same as the previous interval..
Note 5;lf the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.Note 6: The provisions of Specification 4.0.2 are applicable for all inspec-tion intervals up to and including 48 months. I~r.)1 P olg f V r p)sa N A f N p P~'I Ik C TABLE 3.7-4 SAFET RELATED HYDRA IC SNUBBERS*BBER<<0 GER~BK NO.SYSTEM SNUBBER NSTALLED ON LOCATION ELEVATION ACCESSIBLE OR INACCESSIBLE HIGH RADIAT ON ESPECIALLY FFICULT ZONE TO 0'3 1-GRC-8519 1-GRC-537-GRC-8538 REACTOR COO T ELEV..683'1/2" PRESSURIZER E LOSURE REACTO COOLANT AZ 25 ELEV 0'-5" BETWEEN TEM.GEN.O.1 AND RC P P NO.1 ACTOR COOLANT z 41 0 LEV.614'-10" ELOW STM.GENo NO 1 NO YES NO 0 NO 1-GRC-S555 REACTOR C T Az 141 0 ELEV.61-2" BELOW STM.GEN NO 2 1-G-S562 REAC R COOLANT Az 154 0 EL 610'-5" BETWEE STM G.NO.2 AND RC P P NO.2 1-GRC-S564 REACTOR COOLANT 313 0 ELEV.614'~10 1 8" BELOW STM.GEN NO.4 NO YES NO NO NO NO 1-GRC-S5 6 1-RC-S573 REACTOR C T Az 332 ELEV 610'BETWEEN STM.GEN NO.4 AND RC PUMP NO.4 REACT R.COOLANT Az 223 0 ELE 614'-10 1/8" BELO STM.GE.NO.3 ES NO NO NO*Funct nal testing of th s snubber may be layed until the irst time the un enters Mode 5 ter September 1989 or in con)unctio with the schedule ice condenser ic basket surveill nce, whichever o cure first.PLANT-UNI 1 3/4 31 AMEND T NO 128
T E 3.7-4 SAFETY REL ED HYDRAUL SNUBBERS*NUBBER~O HANGER RK NO 1-GR 8575 1-GRC-8582 1-G-8587 SYSTEM NUBBER INS LED ON LO TION AND EVATION RE TOR COOLAN Az 208 E V.610'-5" ETWEEN STM EN'O.3 D RC PUMP N.3 REACTOR LANT Az 21 ELEV 6'-4" NEAR CTOR CAVIT WALLi ACROS FROM STM EN.NO.3 ACTOR COOL Az 260 O LEV 622'-4/4" IN CONTAINMEN ACCESSIBLE R NACCESSI E Y S 0 YES 0 H GH RADIATION ESPECIALL DIFFICULT ZON 0 OVE 12 13 15 16 1-GRC-S59 1-G-8594 1-GRC-8596 1-GRC 598-GRC-8599 REACTOR OOLANT Az 29 ELEV 6'-6 3/4" IN PRESS IZER ENCLOS RE CTOR COOLANT z 292 EV 691'-9" I RESSURIZER E LOSURE.REACTOR C ANT Az 285 O ELEV 691-'N PRESSURI ER ENCLOSURE. REACT COOLANT Az 2 0 ELEV 670'-3 3/4" IN P SURIZER ENCLOS RE.ACTOR COOLANT z 287 ELEV 672'-4" I PRESSURIZER E CLOSURE.0 0 0 0 Y S 0/COOK NU EAR PLANT-U T 1 3/4 7-32 AME DMENT NO.71 ~[h t(r TABLE.7-SAFE RELATED YDRAULIC SN BBERS*SN BER 0.17 HANGER K 0 1-GR 8604 SYS M SNUBBER NSTALLED 0 OCATION A ELEVATIO ACTOR COO T Az 286 LEV 688'-" IN PRESSURIZ ENCLOSU ACCES BLE OR INAC SSIBLE HIGH ATION ESP CIALLY DIF ICULT Z E TO E OV 0 18 19 20 21 22 24-GRC-8608 1-GRC 614 FW-S1 1-FW-S2)1--S2(U)1-FW-S3 1-FW-S (L)REACTO COOLANT Az 86 ELEV 3'-0" IN PRES RIZER ENCL SURE.RE CTOR COO Az 282 EV 681'-0" N RESSURIZER NCLOSURE.FEEDWATER z 31 ELEV 634-9" BEHIND S GEN NO.1 FEED TER Az 26 ELE 633'-6" BEHI D STM GE NO.1 EDWATER Az 2 LEV 636'-0" EHIND STM GEN NO.1 FEEDWATER z 20 ELEV 629'" BEHIND ST GEN NO.FEEDW ER Az 154 ELEV 636'-8 3/8" B IND STM GEN NO.2 0 0 0 0 0 C K NUCLEAR PL T-UNIT 1 3/7-33 AMEN NT NO.71 lg' TABLE 3.7-S FETY LATED YD LIC SNUBBER*UBBER~O.26 27 28 29 HANGER~RK~O.1-FW-(U)-FW-S5 1-FW-S6 1-W-S7 1-FW-SB(SYSTE SNUBBER IN ALLED ON TION AND EVATION PE WATER Az 1 E V 640'-8 3" BEHIND TM GEN NO.FEEDWATER z 163 ELEV 634-9" BEHIND M.GEN NO.2 PEED TER Az 157o EL 629'-9" BE ND STM.G NO.2 EEDWATER A 204 ELEV 634'-'EHIND STM GEN NO.3 PEEDWA R Az ELEV 3'-6" BEHIN STM.GEN 3 ACCESSIBLE R INACCESSI LE HI RADIATION ESPECIALL DIFFICULT ZONE TO 0 NO NO NO 30 1-SB (U)1-FW-S9 1-FW-Sl (L)F DWATER Az, 2 EV 636'-0" HIND STM.EN NO.3 FEEDWATER z 194 ELEV 629'" BEHIND ST GEN NO, 3 PEED TER Az 334 ELE 633'-6" BEHIN STM.GE NO.4 NO NO K NUCLEAR P T-UNIT 1/4 7-34 AMENDMENT NO.7. T LE 3.7-4 SAFETY RE ED HYDRAULIC NUBBERS*SN BER 0 33 35 HANGER Q~RK~0 1-FW-0(U)-FW-811 1-FW-S-GCS-8634 SYSTEM NUBBER INST LED ON LO AT ON AND E ATION FE ATER Az 33 E V 636'-0" B IND STM.N NO.4 FEEDWATER z 330o ELEV 634'" BEHIND ST GEN NO.4 FEE ATER Az 343 EL 629'-9" BEH D STM.N NO.4 CHEM6VOL CON OL Az 292 ELEV 613'ONTAINMENT AC SSIBLE OR ACCESSIBLE HIGH IATION ES CIALLY DIF ICULT ONE 0 EMO NO 0 NO YE 37 38 39 40 1-GCS-86 1-G-8757 1-MSS-1 1-MS 2 CHEMGVO , CONTROL Az 7 ELEV 6'-10" IN ANN US.RC MP SEAL HATE SUPPLY, B WEEN RC PUMP.2 AND E WALL, I DIATELY UNDE GRATING Az 12 ELEV.612'- 1/8" MAIN STEAM z 8 ELEV 639'/4" BETWE STM GEN 0.1 AND NO.4 MAIN TEAM Az 17 ELE 635'ETWEEN STM.GE NO.1 AND N.4 0 NO 0 41 1-MSS-3 COOK NUC AR PLANT-UNI 1 IN STEAM A 172 ELEV 639'-1/4" BEHIND S GEN NO.1 3/4 7-35 AMENDMENT NO.71 1 i+I TABLE 3.-4 SAFET RELATED HY AULIC SNUB RS*UBBER~O.42 HANGER R 1-M S-4 SY EM SNUBBER STALLED 0 LOCATIO AN ELEVATIO ain Steam A 165o Elev.35'etween Stm Gen.No.2 nd No.3 ACCESS LE OR INACC SIBLE HIGH RADIAT N ESPECIALL DIFFICULT ZO E 0 OV 45-MSS-5 1-MSS-6 1-S-7 1-MSS-8 Main Ste Az 191 El.635'etween tm.Gen.No 2 and No.Main team Az 184 0 Elev 639'-1 1/4" Between St Ge.No.2 and o.3 ain Steam Az 349 Elev.5'Behind Stm.en.No.1 a d No.4 Main Ste Az 356 o Elev.6'-1 1/4" B ween Stm.Gen.No 1 and No.NO 0 0 0 NO 47 50 51 1-GCCW 278 1-G CW-S309 1-GCCW-S837 1-GCCW-8 38 1-GC-8839 Comp ent Cooling ater Ele.609'n C Pump Area C ponent Coo ng Water lev.597'-1/8" In Pass eway Near Sampli g Room Aux.dg.Componen Cooling Wate E1ev.1'0" In CCW Pump Area Compo ent Cooling ter Elev 621'-0" In W Pump Area C ponent Cooli g Water ev.621'-0" n CCW Pump A a 0 0 0 K NUCLEAR P T-UNIT 3/4 7-36 AME MENT NO.104 33 3'433~'3 3 33 TABLE 3.SA E RELATED YD LIC S UBBE S*SN BER 0 52 53 55 56 GER RK NO.1-GCCW-S8 1-GC-S841-GCCW-8842 1-GCCW-S84 1-GBD 563 GBD-8569 SYSTEM SNUBBE INSTALLED 0 LOCATIO D ELEVATIO COMPONENT OOLING WATER ELEV 62'-0" IN CCW PU AREA COMP ENT COOLING W ER ELE.621'-0" IN C PUMP AREA OMPONENT COOLI G WATER ELEV.621'-0" N CCW PUMP AR COMPONENT LING WATER ELEV.60-0" IN CCW PU AREA, STM.N.BLOWDOWN A 277 ELEV 608'-6 1/2" ANNULUS M.GEN.BLOWD N Az 278 LEV 608'-6 1" IN ANNULUS ACCESSIBLE R INACCESSI HIGH IATIOQ ESPE ALLY DIFFICUL ZO E 0 E 0 0 NO 0 0 0 58 59 61 1-GBD-8573 1-GBD-74 1 RH-S7A 1-GRH-S7B STM.GEN.B OWDOWN Az 181 ELEV.607'0 1/2" IN AN LUS STM.G.BLOWDOWN Az 81 ELEV 607'-10 1/2" ANNULUS IDUAL HEAT RE VAL LEV.581'-8 1/" IN I-E RHR PUMP ROOM RESIDUAL H T REMOVAL ELEV 58-4" IN I-E RH PUMP R 0 0'0 COOK NUCLEAR T-UNIT 1 3/7-37 NDMENT NO.7 ls ~~SAFETY ELATED YDRAU C SNUBBERS*SNUBBER 0 6 63 64 65 66 68, 70-GRH-S47 1-GRH-S4 1-DG-S13 1-GDG-S14 1-GS 8103 1-GSI-8128 1-GSI-75-GSI-8657 1-GSI-8707 SYS M SNUBBER I TALLED ON OC TIO AN ELEVATION esidual Hea Removal Elev.581'1-W RHR Pump Roo Resid 1 Heat Remova Elev 580'-6" In 1 RHR Pu Room-AB Emerg.D sel Exhaust Elev.596'-3/8" 1-AB Emer.Diesel Exhau Elev.6'-6" Safe Injection El.573'n 1-E R P mp Room Safety In)ecti n Elev.573'1-W RHR Pump Room Safety)ection Elev.8'-9 3/8" Az 6 In A ulus S ety In)ection z 185 0 ev.610'-0" I Annulus Safety In)ec ion Az 228 0 Elev.608'/8" Behind RC Pump N.3 ACCESSIBLE 0 INACCESSIB HIGH IATION E ECIALLY DIF CULT 0 E 0 EMO NO 0 0 0 ES 0 0 COO NUCLEAR PLANT-IT 1 3/4 7-3 NDHENT NO.104 TABLE.7-SA TY RELATED DRAULIC SNUB RS*SNU ER 0 GER 0 SYSTEM SNUBB INSTALLED 0 LOCATIO D ELEVATI ACCESS LE OR INACC SSIBLE IGH RADIAT N ESPECIAL DIFFICULT ONE 0 OVE 71 1-GCTS-S73 )CONTAINMEN SPRAY ELEV.5'-0" IN I-E CONTAI ENT SPRAY P P ROOM 0 72 74 75 76 77 1-GCT-873(W)-GCTS-876(B) 1-GCTS-6(A)1-CTS-S160A (N)1-GCTS-S16 A (S)1-GC-8161 (E)-GCTS-S161 (W)CON INMENT SPRA EL 582'-0" I I-E NTAINMENT SP Y PUMP ROOM CONTAINMENT SPRAY ELEV 579'" INSIDE LEA DETECTOR OXt PIPE CHAS CONTA MENT SPRAY ELEV 579'-6" INSID LEAK DET CTOR BOX'IP CHASE NTAINMENT SP ELEV.582'-0" NSIDE LEAK DETECTOR BOX PIPE CHASE CONTAINMEN SPRAY ELEV.58-0" INSIDE L K DETECTO BOX'IPE C E CONTA MENT SPRAY ELEV.579'-6" IN W CO AINMENT SPRA PUMP ROOM ONTAINMENT SP Y ELEV.579'6" N I-W CONTAINMENT PRAY PUMP R A NO 0 0 0 0 COOK NU EAR PLANT-UN 1 3/4 7-39 NDMENT NO.71 I-f0 TABLE 3.7-4 SAFET RELATED HYDRA IC SNUBBERS*UBBER~O 79 80 GER Q~R~O.N/A/A SYSTEM SNUBBER NSTALLED 0 LOC TIO D ELEV TIO STEAM GENE TOR NO.1 ELEV.66 STEAM ENERATOR NO.ELEV 665'CCESSIBLE I CCESSIB HIGH IATION ESPE ALLY DIFFICULT 0 0 OV ES 81 N/A EAM GENERATOR LEV.665'.1 YES 82 83 N/A STEAM GENE TOR NO.1 ELEV 665 STEAM ENERATOR NO+2 ELEV 665'4 N/A S AM GENERATOR LEV 665'2 ES 85 86 N/A N/A STEAM GENE OR NO.2 ELEV 665'TEAM G ERATOR NO.2 ELEV 65'T GENERATOR NO.EV.665'88 N/A STEAM GENERATO ELEV.665'O.3 0 89 N/STEAM GENE TOR NO.3 ELEV.66 K NUCLEAR P-UNIT 1 3/4 7-40 AME NT NO 71 LE 3 7-SAFET L ED YDRAUL C S BBE S*SNUBBER~O 90 92 93 94 HANGER N/A N/A N/N/A N/A SYSTE SNUBBER INST ED ON AT ON N EL ATIO ST GENERATOR o 3 EV.665'TEAM GENE OR NO.4 ELEV.665'TEAM G ERATOR NO.4 ELEV.65'TE GENERATOR NO 4 E V.665'TEAM GENERATO NO.4 ELEV.665'C SSIBLE OR I CCESSI E HIGH RADIA ON ESPECIAL DIFFICULT ZO OVE ES nubbers may added to safe related syst s without prio License Amendment to able 3.7-4 pro ded that a re ision to Table.7-4 is included w the next Lic se Amendment quest.Modific ions to the"H h Radiation 2 e" column due changes in h h radiat n areas may be ade without p or License Ame ent provided hat a rev sion to Table.7-4 is includ with the next icense Amendme COOK NUCLEAR T-UNIT 1 3/4 7 40a NDMENT NO.71 3*l tg C;~W,kl II'MO BASES Co ti ued The visual inspection freque c is based u n maintainin a constant level of snubber rotection to s stems.T e efore, e requi d ns t on nt rva var s nve sely w e o served s bber fai ures and is dete ined by he numb r of i operab snubb s found uring an inspecti n.Ins ctions per rmed fore t at inte val has apsed m be use as a ne referen e point to etermi e the xt ins ction.owever, he resul s of su h early in etio perfo ed bef e the or ginal re ired ti e inter 1 has el psed (n minal ime less 25%a not b used to en then he re ed ns ction interval.Any nspection whose resu s requ re a shorter nspection interval w override the previous schedule.When the cause of the re)ection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible,snubbers are those which are of a specific make or model and have the same design features directly related to refection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration. When a snubber is found inoperable, an engineering evaluation is performed,, in addition to the determination of the snubber mode of failure, in order to determine if any safety>>related component or system has been adversely affected by the inoperability of the snubber.The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 24 month intervals. Observed failures of these sample snubbers shall require functional testing of additional units.The service life of a snubber is evaluated via manufacturer's input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc...).The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation. The number of snubbers to be functionally tested during each surveillance is based on calculations performed to allow extension of the surveillance interval from 18 months to 24 months, and therefore, the number of snubbers functionally tested deviates from the number required by the Westinghouse Standard Technical Specifications (NUREG-0452, Revision 4).MmSe,rY z, W COOK NUCLEAR PLANT-UNIT 1 B 3/4 7-6 AMENDMENT NO.494g 116 Insert C (Page B 3/4 7-6)The method for determining the next interval for the visual inspection of snubbers is provided based upon the number of unacceptable snubbers found during the previous inspection, the category size for each snubber type, and the previous inspection interval per NRC Generic Letter 90-09.A snubber is considered unacceptable if it fails to satisfy the acceptance criteria of the visual inspection. Insert D (Page B 3/4 7-6)A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c)of 10 CFR Part 50.The accessibility of each snubber shall be determined and approved by the Plant Nuclear Safety Review Committee. The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.The addition or deletion of any snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50. p C'I J J~lk ADMINISTRATIVE CO OLS 6.10.2 The following records shall be retained for the duration of the Facility Operating License: a.Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.b.Records of new an irraPiated fuel inventory, fuel transfers and assembly burnup histories. c.Records of radiation exposure for all individuals entering radiation control areas.d.Records of gaseous and liquid radioactive material r'eleased to the environment. e.Records of transient or operational cycles for those facility components identified in Table 5.9-1.f.'ecords of reactor tests and experiments. g.Records of training and qualification for current members of the Plant Staff.h.Records of in-service inspections performed pursuant to these Technical Specifications. i.Records of Quality Assurance activities required by the QA Manual.Records of reviews performed for changes made to procedures or equipment or review of tests and experiments pursuant to 10 CFR 50.59.k.Records of meetings of the PNSRC and the NSDRC.1.Records of radioactive shipments. m, Records of the service lives of hydraulic snubbers~d-ea associated installation and maintenance records.6 11 RADIATION PROTECTION PROG Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.6 12 HIGH RADIATION AR 6.12.1 In lieu of the"control device" or"alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and COOK NUCLEAR PLANT-UNIT 1 6-20 AMENDMENT NO.80, 154 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3 4.7 PLANT SYSTEMS (Continued) PAGE 3/4.7.9 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System Spray and/or Sprinkler Systems Low Pressure C02 Systems Halon System Fire Hose Stations 3.4.7.10 FIRE RATED ASSEMBLIES 3 4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.SOURCES Operating Shutdown~~~~~~~~~0~~I~~3/4 7-A Z7 3/4 7-39'3o 3/4 7-K 3+3/4 7-Q 3ts 3/4 7-&37 3/4 7-m 39 3/4 8-1 3/4 8-9 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C.Distribution-A.C.Distribution '-D.C.Distribution-D.C.Distribution-D.C.Distribution-Operating Shutdown Operating Shutdown Operating-Train N Battery System 3/4 8-10 3/4 8-11 3/4 8-12 3/4 8-16 3/4 8-17 3/4.9.1 BORON CONCENTRATION 3/4.9.2 INSTRUMENTATION 3/4.9.3 DECAY TIME 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS 3/4.9.5 COMMUNICATIONS 3/4.8.3 ALTERNATIVE A.C.POWER SOURCES 3 4.9 REFUELING OPERATIONS 3/4 8-20 3/4 9-1 3/4 9-2 3/4 9-3 3/4 9-4 3/4 9-5 COOK NUCLEAR PLANT-UNIT 2 IX AMENDMENT NO.112 g)C-"-.h'I f c.y Q r-'~adp S ST BEST.The service life of a snubber is evaluated via manufacture's input and information through consi'deration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc...).The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation. The number of snubbers to be functionally tested during each.surveillance is based on calculations performed to allow extension of the surveillance interval from 18 months to 24 months, and therefore, the number of snubbers functionally tested deviates from the number required by the Westinghouse Standard Technical Specifications (NUREC-0452, Revision 4).3 4 7.8 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c)limits for plutonium. This limitation will ensure that leakage from byproduct, source and special nuclear material sources will not, exceed allowable intake values.3 4 9 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located.The fire suppression system consists of the water system, spray and/or sprinklers, C02, Halon and fire hose stations.The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.In the event that one or more C02 Suppression System requiring automatic actuation must be isolated for personal protection to permit entry for routine tours, maintenance, construction, or surveillance testing in the protected area, the fire.detection system(s)required to be operable by Specification 3.3.3.7 shall be verified to be operable.Isolation of an automatic C02 suppression system temporarily puts this system in a manual actuation mode.Reliance on the fire detection system, in conjunction with the ability to manually discharge the C02 suppression system will provide adequate fire protection for periods when personnel are required to work in these areas.COOK NUCLEAR PLANT-UNIT 2 B 3/4 7-6 AMENDMENT NO.97, 102, ill, 115 Insert H (Page B 3/4 7-6)A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c)of 10 CFR Part 50.The accessibility of each snubber shall be determined and approved by the Plant Nuclear Safety Review Committee. The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.The addition or deletion of any snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50. LIMITIN TIO FOR OPERATION Soph'r~3.7.7.1 All snubbers shall be OPERABLE.APPLICABILITY: MODES 1, 2, 3 and 4.(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).ACTION: With one or more snubbers inoperable, within inoperable snubber(s) to OPERABLE status and per Specification 4.7.7.l.c on the supported system inoperable and follow the appropriate SURVEILLANCE RE UIREMENTS 72 hours replace or restore the perform an engineering evaluation component or declare the supported ACTION statement for that system.4.7.7.1 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.Visual s ecti T~s~j The rst in rvice vi al inspe ion of ubbers ll be pe-fo ed aft four mon s but w h 10 mon s of co ncing P R 0 RATION and shall nclude a snubbe listed i Table 3-9.f less han two (snubbe are fou inoper e during the first service sual ins ection, t e second service isual insp tion shal be perf ed 12 m ths plus r minus 0 from the date of t first i spection.Otherwis ,subseque visual i pections all be rformed accordan e with t followi g chedule: No.Ino rable Sn hers er In ection P riod Subse ent Visu Ins tion Per d*3,4 5,6,7 8 or re 18 months pl s or min 25%months us or mi s 25%6 months lus or nus 25%124 days plus or nus 25%62 day plus or nus 25%31 da s plus or inus 25%Th snubbers ay be cate rized in two gro s: Those ccessible d those i ccessible uring rea or opera on.Each group may e inspect d independ tly in ac ordance w h the abo e schedule.*he ns tion nte al all got begengthpfied mg/e thangne stegat a me.Th pro isio of peel catp6n 4.Q2 areQot app1.icable/ COOK NUCLEAR PLANT-UNIT 2 3/4 7-20 AMENDMENT NOi SV~4QDg 131 n 1 l l~t~WI1-1~X J'W 17 L 4 h t t Insert E (Page 3/4 7-20)Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be, inspected independently according to the schedule determined by Table 3.7-9.The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 3.7-9 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment No. t hw I)Al."iC 4 PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued b.V sual Ins ction Acce tance Criteri 4-l(he C.hoSS'Wick a.s v g~gc.e.g(~bEe o.~b.~y'w~~c 4<sq.~gg.q(~able Visual inspections shall verify (1)that there are no visible indica-tions of damage or impaired OPERABILITY, (2)attachments to the foundation or supporting structure are secure, and (3)in those locations where snubber movement can be manually induced without dis-connecting the snubber, that the snubber has freedom of movement and is not frozen u.Snubbers which appear inoperable as a result of visual nspec ons for the purpose of esta-blishing the next visual inspection interval, providing that-(1)the cause of the re)ection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2)the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specifications c~All snubbers'connected to an inoperable common hydraulic fluid reservoir shall be counted as~AMrk"iypg Functional Tests At least once per 24 months during shutdown, a representative sample (14%)of the total of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test..For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.7.1.d an additional 10%of that type of snubber shall be functionally tested.1.The first snubber away from each reactor vessel nozzle 2.Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc.)3.Snubbers within 10 feet of the discharge from a safety relief valve~k are SnubbersYidentified as"Especially Difficult to Remove" or in"High Radiation Zones During Shutdown" shall also be included in the representative sample.The representative sample selected for functional testing shall incgude the various configurations, operating environments and the range of size and capacity of snubbers.At least 25%of the snubbers in the representative sample shall include snubbers from the following three categories:
Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a)ustifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.COOK NUCLEAR PLANT-UNIT 2 3/4 7-21 AMENDMENT NO.9&i kB&, 131 Insert F (Page 3/4 7-21)unacceptable for determining the next inspection interval.A review and evaluation shall be performed and documented to)ustify continued operation with an unacceptable snubber.If continued operation cannot be)ustified, the snubber shall be declared inoperable and the ACTION requirements shall be met.
+X LE c~'>>Y 1 4 gl 4g'At PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued Zn addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.Zf a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position)and the spare snubber shall be retested.Test results of these snubbers may not be included for the re-sampling. Zf any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested.This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.For the snubber(s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber(s). The purpose.of this engineering evaluation shall be to determine if the components supported by the snubber(s) were adversely affected by the inoperability of the snubber(s) in order to ensure that the supported component remains capable of meeting the designed service.d.H draulic Snubbers Functional Test Acce tanc Cr te The hydraulic snubber functional test shall verify that: 1.Activation (restraining action)is achieved within the specified range of velocity or acceleration in both tension and compression. 2.Snubber bleed, or release rate, where required, is within the specified range in compression or tension.For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.e.Snubber Service Life Monitorin A record of the service life of each snubber, the date at which the designated service life commences and the installation and mainten-ance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.Concurrent with the first inservice visual inspection and at leapt gngy~per 1)~g months thereafter, the installation and maintenance records for'24Ms ub8ers shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.Zf the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review.This reevaluation, replacement or reconditioning shall be indicated in the records.COOK NUCLEAR PLANT-UNIT 2 3/4 7-22 AMENDMENT NO 53 'w'\~C ~nor<Ta.bLe-TABLE 4'.7-Z'+SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Population Co umn A Co umn B Co umn C'r Category Extend Interval Repeat Interval Reduce Interval Notes 1 and 2 Notes 3 and 6 Notes 4 and 6 Notes 5 and 6 80 0 100 150 200 300 12 13 25 400 500 750 1000 or greater 12 20 29 18 40 56 36 48 78 109 Note 1: Note 2: Note 3: Note 4: The next visual inspection interval for a snubber population or cate-gory size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval.Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible. These categor-ies may be examined separately or jointly.However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.Interpolation between population or category sizes and the number of unacceptable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B, or'C if that integer includes a fractional value of unacceptable snubbers as determined by inter-pol ation.If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.If the number of unacceptable snubbers is equal to or less than the number in Column B but greater that the number in Column A, the next inspection interval shall be the same as the previous interval. Note 5: If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column 8, the next interval shall be reduced proportionally by interpolation, that is, the previous interval sha'll be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column 8 to the difference in the numbers in Columns 8 and C.Note 6: The provisions of Specification 4.0.2 are applicable for all inspec-tion intervals up to and including 48 months. h l C 4 4 f.0 C , H'*~ray<e~~I e~1~t III e~os~r<W s TABLE 3.SAFET RELATED HY AULIC SNUBB S*NUBBER~O.HANGER A K'-GR-8537-GRC-8538 SY EM SNUBBER STALLED ON LOCA ION N ELEVATION ACTOR COOL T AZ 25 ELEV 610'-5 STM.GEN.N.1 REACTOR LANT AZ 41 ELEV 61-10" RC PUM NO.1 ACCESSIB OR INACCES BLE IGH RADIAT N ESPECI Y DIFFICULT ZONE T E 0 0 YES 2-GRC-SS REACT COOLANT AZ 41 ELEV 614'-10" 1/8 RC PUMP NO.ES 0 10 2-G-8562-GRC-8564 2-GRC-S 6 2-GR-8573-GRC-8575 2-GRC-8582 2-GRC-S 2 ACTOR COOL AZ 154 LEV 610'-5" TM GEN.NO.REACTOR C ANT AZ 317 ELEV 614'0" 1/8" RC MP NO.4 REACT COOLANT AZ 1 O ELEV 10'-5" STM G.NO.4 RE CTOR COOLANT Z 223 EV 614'-10"/8" RC PUMP 0.3 REACTOR COOL T AZ 208 ELEV 610'-5 STM GEN.NO 3 REACTOR LANT AZ 208 ELEV 617-4" 7/8" ST.GEN.NO.3 REACT COOLANT AZ 82 ELEV 683'-3 1/8" PRESSURIZE ENC OSURE 0 0 0 0 0 0 0 K NUCLEAR P-UNIT 2 3 4 7-23 NDMENT 0.53 I 1, pg T BLE 3.7-9 SAFETY REL ED HYDRAULIC SNUBBERS*UBBER~O.HANGER/ARK~0.2-GRC-S59 SYSTEM UBBER INST ED 0 LOC ION AND ELE TIO REACT R COOLMT AZ 91 ELEV.683'-3 9/16'N P SURIZER ENCL SURE AC SSIBLE OR I CCESSIBLE HIGH RAD TION ESPEC LY DIFFICULT ZO 0 EMOVE 0 12.13 14 16 17 2-GR 8596-GRC-8598 2-GRC-S5 9 2-G-8609 2-GRC-8611 2-GRC-S62 2-GRC 8624 ACTOR COOLAN AZ 292 LEV.682'-ll 1/8" IN PRESSURIZER NCLOSURE REACTOR C LMT AZ 279 ELEV.67-5 1/4" IN PRESSUR ER ENCLOSURE REACT COOLMT AZ 2 9 ELEV 672'-4 1/2" I PRE SURIZER ENCLOS R ACTOR COOLMT Z 283 LEV.689'-5/16'N PRESSURIZER EN LOSURE REACTOR COOL T AZ 294 ELEV.681'-7/8" IN PRESSURIZE ENCLOSURE REACTOR OOLMT AZ 277 ELEV.6 2'-9 1/16" IN PRESSU IZER ENCLOSURE REAC OR COOLANT AZ 47 ELE.615'-6" ABOV RELIEF T K NO 0 0 YES 0 NO COOK NUCLE PLANT-UNIT 2 3/7-24 AHENDHE T NO.53 TABLE 3.FETY RELATED Y ULIC SNUBBER NUBBER~O.19 20 GER~R(NO.2-GRC-S62 2-G-8629 SYSTEM SNU ER INSTALLED ON OCATI AND ELEVATION REACTOR OOLANT AZ 284 ELEV.92'-3/16" IN PRES RIZER ENCLOSU CTOR COOLANT A 283 LEV.687-4 1/16'N PRESSURIZER EN OSURE ACCESSIBLE R INACCESSI E HI RADIATION ESP IALLY DIFFICU ZON 0 E 0 NO 21 2-GRC-8630 REACTOR COO T AZ 291 ELEV.672'l/16" IN PRESSURIZ ENCLOSURE NO 0 22 23 24 2-GRC-S 32 2 RC-8631 2-GRC-8587 2-FW-S REACTO COOLANT AZ 291 ELEV.669'-3 ll/16" I PRE URIZER ENCLOSUR ACTOR COOLANT A 291 LEV.670'-ll 11 6" IN PRESSURIZER ENC OSURE REACTOR COOL T AZ 260 ELEV.622'-1/4" BY RELIEF TANK FEEDWAT R AZ 31 ELEV.34'-9" NEAR STM GEN.0.1 0 0 0 26-FW-S2(L)F DWATER AZ 26 EV.633'-6" NE STM.GEN.NO.1 NO COOK UCLEAR PLANT-UN 2 3 4 7-25 AMENDMEN NO.5: ,4 4w~I 1"%48 L'* TABLE 3.7-9 SAF Y RELATED HYD LIC SNUBBERS*SNUBBER~O 27 HANGER$~~0;2-FW-S2(2--S3 SYSTEM SNUBB INSTALLED 0 LOCATIO AND ELEVATION FEEDWATE AZ 26 ELEV.6'-0" NEAR STM.N.NO.1 F DWATER AZ 20 LEV.629'-9" N STM, GEN, NO.ACCESSIBLE IN CCESSIB HIGH IATION ESPEC LY DIFFICULT ON 0 E 0 0 29 31 32 2-FW-S4(L) 2-FW-4(U)2-FW-SS 2-FW-S6 FEEDWATER A 155 ELEV.637'" NEAR STM.GE NO.2 FEED TER AZ 155 ELE.641'-0" NEAR S~GEN.NO 2 FEEDWATER AZ 1 ELEV.634'-9" NEAR STM.GEN.N 2 FEEDWATE AZ 157o ELEV.9'-9" NEAR STM.N.NO.2 0 0 0 0 33 34 2--S7 2-FW-SB(L) F DWATER AZ 204 EV.634'-9" NE STM.GEN.NO.3 FEEDWATER AZ 00 ELEV.633'-" NEAR STM GEN, 0.3 0 0 0 2-FW-S (U)COOK NUCLEAR P T-UNIT 2 FEEDWA R AZ 200 ELEV.636'-0" NEAR STM GEN.NO.3 3/4 7-26 0 AMEN NT NO.53 Ig~I TABLE.7-9 FETY RELATED DRAULIC S UBB RS*SNUBBER~O.36 38 39 HANGER~/~0.2-FW-S9 2-FW-0(L)-FW-810(U) 2-FW-Sll 2--S12 SYSTEM SNU ER INSTALLED ON LOCATI AND ELEVATIO Feedwat Az 194 0 Elev.29'-9" near Stm.en.No.3 F dwater Az 334 0 ev.634'-0" n r Stm.Gen.No.Feedwater A 334 o Elev.636Žnear Stm.Gen.o.4 Feedwa r Az 330 0 Elev.634'-9" near Stm.Gen.No.4 F edwater Az 343 o lev.629'-9" ne Stm.Gen.No.4 ACCESSKB OR INACCES IBLE HI RADIATION E ECIALLY DIFFI ULT 0 E 0 EOE 0 0 0 0 0 42 44 45 2-GBD-8563(L) 2-GBD-S56 (U)2-GBD 8569(L)2 GBD-S569(U) 2-GBD-S568 Stm.Gen.Bl down Az 275 o Elev.607'-" In Annulus Stm.Gen.lowdown Az 275 o Elev.60'-6" In Annulus o Stm.n.Blowdown Az 75 Elev 607'-ll" In An lus S.Gen.Blowdown z 275 ev.608'-6" In nnulus Stm.Gen.Blow wn Az 2644 Elev.608'-1" n Annulus 0 0 0 0 0 0 COOK CLEAR PLANT-UN I 2 3/7-27 AMENDME NO.91 , lt'A!0 I~ TABL 3.-9 PETY RELATE HY RAULIC S E S*SNUB R 46 49 GER R 0.2-GRH-S6 2-GRH-S 2-G-S24-GRH-S25 SYSTEM SNU ER INSTALLE ON LOCATI AND ELEVA ON Residua Heat Remova Elev.1'-6" RHR P mp Room 2E Res ual Heat Re val El.581'-3" Pump Room 2E esidual Hea Removal Elev.581'-RHR Pump Roo 2W Residual eat Removal Elev.58'-6" RHR Pump oom 2W ACCES BLE OR INAC SSIBLE HIGH RADIATI ESPECIALLY IPFICULT ZO E 0 0 0 0 0 50 2-GCCW-S2 Compo nt Cooling Wa r Elev 621'-0" CCW P p.Area 0 0 51 2-GCC 8308 C ponent Cooling ater ev.610'-1/2" CW Pump Area 0 0 52 53 54 56 2-CCW-S317 2-GCCW-S320 2-GCCW-19 2-G W-S521-GCCW-8550 Component Coo ng Water Elev.621'-0" CCW Pump Area Component ooling Water Elev.610-6" CCW Pump ea o Compon t Cooling Wat Az 132 Elev.23'-4" RC Pum Area 0 Com onent Cooling ater Az 132 El v.624'-9" RC ump Area omponent Cool g Water Az 308 0 Elev.619'-3" C Pump Area 0 0 0 0 0 0 COOK NUC PLANT-UNI 2 4 7-28 AMEND NT NO.91 II p P .T BLE 3.7 SA TY RELA ED HY AULIC SNUBBER NUBBER~O 57 HANGER~R~O.2-GCCW-S83 SYSTEM SNUB R INSTALLED 0 LOCATIO AND ELEVATIO Componen Cooling Water Elev.6 1'-0" CCW Pump rea ACCESSIBLE R INACCESS L HIGH IATION ESPEC LY DIFFICULT 0 E 0 NO 58 59 60 2-GCC 8839 GCCW-S840 2-GCCW-8843 Com nent Cooling W er El.621'-0" CCW ump Area omponent Cool g Water Elev.620'-0" CW Pump Area Component ooling Water Elev.62-5" CCW Pump Ar a 0 0 61 62 2-GCCW-06 2-G-S634 Compo nt Cooling Elev 596'-2 3/8" C m&Vol.Control lev.613'-'1" In by No.4 RC Pum Wate C Pump Area z 299 de crane wall 0 0 0 63 66 2-GCS-8637 2"GCS-87 9 2-M-1 2-MSS-2 Chem&Vol.Co rol Az 72 o Elev.608"-0" In Annulus Chem&Vol Control Az 234 0 Elev.7"-0" RC Pump Ar Mai Steam Az 8 o El.639'-1 1/4" Be een S.Gen.No.1 and 4 Main Steam Az 17 o Elev.635'-0" B ween Stm.Gen.No.and 4 0 NO" 0 COO NUCLEAR PLANT-IT 2 3 4 7-29 AMENDMENT NO.91 I l'I4 TABLE 3.SA TY ELATED H RAULIC SNUBBE S*UBBER~O 67 HANGER/ARK~0'.2-MSS-3 SYSTEM SNUB R INSTALLED 0 OCATIO ND LEVATION MAIN STE AZ 172 ELEV 6 9'-1 1/4" BET EN STM.N.NO.2 AND ACCESSIB OR INACCES BLE HIG RADIATION E ECIALLY DIFFIC T ZO TO E OV 0 69 70 72 74 2-MSS-MSS-5 2-MSS-6 2-SS-7 2-MSS-8 2-GSI 47 2 SI-S51 MA STEAM AZ 165 E Vo 635'-0 BE EEN TM GEN NO.AND 3 MAIN STEAM 191 ELEV.635'BETWEEN STM.GEN NO.2 AND 3 MAIN EAM AZ 184 ELEV 639'-1 1/4" B WEEN ST GEN.NO.2 AN 3 IN STEAM AZ 3 ELEV 635'-0 TWEEN STM.GEN.NO 1 AND 4 MAIN STE AZ 356 ELEV, 63-1 1/4" BETWEEN STM.GE.NO.1 AND 4 SAFE INJECTION SYSTE ELE.573'-0" FETY INJECTION S TEM LEV.573'-0" 0 0 0 0 0 0 ES 75 2-GSI-8575 SAFETY INJECTI SYSTEM AZ 65 ELEV.598'-9/8" IN ANNULUS 0 NO COOK UCLEAR PLANT-NIT 2 3/4 7-30 AMENDMENT 0.53 TABLE.7-9 FETY RELATED DRAULIC SNUB RS*S BBER 0 76 HANGER@ARGO.2-GSI-865 SYSTEM SNU ER INSTALLED ON LOCAT N ND ELEVATI SAFETY JECTION SYSTE AZ 185 ELEV.10'-0" IN ANN US ACCESSI E OR INACCE IBLE H GH RADIATION ESPECIALLY FFICULT ZON TO E OVE NO 77 2-GSI 707 SAF TY INJECTION E V.608'-7" NE STEM AZ 221 RC PUMP NO.0 79 80 82 83 2 CTS-861 2-GCTS-8113 )2-GCTS-13)H)2-G S-8114(N)2-GCTS-8114(2-GCTS-15(N)CONTAINMENT S Y ELEV.579'-3 CTS PUMP AREA CONTAINME SPRAY ELEVe 58 0 CTS PUMP EA CONTA MENT SPRAY ELEV 582'-0" CTS P P AREA C TAINMENT SPRAY LEV.582'-0" IN IDE LEAK DETECTOR BOX P E CHASE CONTAINMENT RAY ELEV.582'-"INSIDE LEAK DETECTOR X PIPE CHASE CONTAIN NT SPRAY ELEV.79'-6" INSIDE AK DETE OR BOX PIPE C SE 0 0 N 0 0 0 0 84 2-CTS-8115(S) CO AINMENT SPRAY EV.579'-6" IN DE LEAK ETECTOR BOX PI CHASE 0 COO NUCLEAR PLANT-U IT 2 3/4 7-3 AMEND T NO.53 r"~i'i..pit~'I TA LE 3 7-9 SA EL TE YD LIC S UBBERS*S BBER 85 GER ISED 2-GCTS-S116 )SYSTEM SNUBB INSTALLED 0 OC 0 AND LEV TIO CONTAIN T SPRAY ELEV.5'-6" 2W CTS Pu Room ction Pipe ACCESSIBLE 0 INACCESS HIGH ATION ESPECI Y DIFFICULT 0 0 87 88 90 91 2-G-S116(W)N/A N/A/A N/A N/A CO AINMENT SPRAY EV 579'-6" 2W TS Pump oom Suction Pi e STEAM GENE OR NO.1 ELEV.665'TEAM G ERATOR NO.1 ELEV, 65'T GENERATOR NO.1 V.665'TEAM GENERATO NO.1 ELEV.665'TEAM GEN TOR NO.2 ELEV.66 0 0 0 0 0 94 N/A N/A N/A STE GENERATOR NO.2 ELE.665'AM GENERATOR N 2 ELEV.665'TEAM GENERAT NO.2 ELEV, 665'TEAM GE RATOR NO.3 ELEV.6 0 0 COOK NUCLEAR P-UNIT 2 3/4 7-32 AMEND T NO+91 N gl 4 TABLE 3 SNUBBER 96 97 98 99 100 10 102 HANGER HBEMK.N/A N/N/A N/A N/A N N/A S E EL E SYSTEM SNUB R INSTALLED OC 0 D EVTO STEAM GE RATOR NO, 3 ELEV.6 5'TE GENERATOR NO.ELE.665'AM GENERATOR 0.3 LEV 665'TEAM GENERA R NO.4 ELEV.665'TEAM GE RATOR NO.4 ELEV.6 STE GENERATOR NO.4 ELE.665'AM GENERATOR NO 4 LEV.665'ICS U E*ACCESSIBLE OR INACCES HI RADIATION SPECIALLY DI ICULT 0 0 0 0*Snubb rs may be added o safety related ystems without rior License Ame ent to Table 3.-9 provided that revision to Ta e 3.7-9 is in uded with the n t License Amendm t request.odifications to e"High Radiatio Zone" column du to'hanges i high radiation areas ay be made withou prior License endment-provi d that a revision to ble 3.7-9 is incl ded with the nex License Amen ent request.COOK NUCLE PLANT-UNIT 2 3/4 7-AMENDMEN NO 53 'dU V~Il MHK 4 6 S V ON SYS The OPERABILITY of the ESF ventilation system ensures that adequate cooling is provided for ECCS equipment and that radioactive materials leaking from the ECCS equipment within the pump rooms following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calculations were assumed in the accident analyses.The 1980 version of ANSI N510 is used as a testing guide.This standard, however, is intended to be rigorously applied only to systems which, unlike the ESF ventilation system, are designed to ANSI N509 standards. For the specific case of the air-aerosol mixing uniformity test required by ANSI N510 as a prerequisite to in-place leak testing of charcoal and HEPA filters, the air-aerosol uniform mixing test acceptance criteria were not rigorously met.For this reason, a statistical correction factor will be applied to applicable surveillance test results where required.3 4 HYDRAULIC SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the syst: em on which they are installed, would have no adverse effect on any safety-related system.~sW The visual inspection frequency is based u on maintaining a constant level of snubber rotection to s stems.erefore, the requ d nspec ion int rva va es inve sely with the obse ed snubbe failures nd is de ermined y the n ber of i operable ubbers fo nd during an inspe ion.I spectio perfo d before hat inte al has el psed may b used as a new eferenc point to determin the next nspection. However, the resu s of uch ear y inspec ions perf rmed befo e the orig nal requir d time i terval has ela sed (nom al time ess 25%not be sed to len then the require ins ec ion inte al.y nspection whose results require a shorter inspection interval will override the previous schedule, When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for, any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration. COOK NUCLEAR PLANT-UNIT 2 B 3/4 7-5 AMENDMENT NO.O7, 408, 111
Insert G (Page B 3/4 7-5)The method for determining the next interval for the visual inspection of snubbers is provided based upon the number of unacceptable snubbers found during the previous inspection, the category size for each snubber'ype/ and the previous inspection interval per NRC Generic Letter 90-09.A snubber is considered unacceptable if it fails to satisfy the acceptance criteria of the visual inspection.}}

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