ML17332A811

Proposed Tech Specs Removing Fire Protection Systems from Licenses

ML17332A811
Person / Time
Site:	Cook
Issue date:	06/20/1995
From:	INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17332A812	List: ML17332A811 ML17334B550
References
NUDOCS 9506280709
Download: ML17332A811 (126)

Text

Docket: No. 315 Page 4 of 6 Amendment: 2. C (4)

No. 31, 194 AdttLxnistrative controls V~&r~&i~ceion as described in the

~sKZ1 be implemented and maintained.

(5) S ent Fuel Pool Sto a e Amendment The licensee is authorized to store D. C. Cook, Unit I. and Unit 2 No. 118, 136, 169 fuel assemblies, new or irradiated up to a total of 3613 fuel assembli.es in the shared spent fuel pool at: the Donald C. Cook Nuclear Plant subject to the following conditions:

Fuel stored in the spent fuel pool shall not have a nominal enrichment greater than 4.95% Uranium-235.

(6) Deleted by Amendment 80.

Amendment ('7) The provisions of Specification 3/4.9.7 are not applicabLe for No. 169 loads being moved over the pool for the duration of the spent fuel pool reracking project. Control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-0612 "Controls of Heavy Loads at Nuclear Power Plants." Admixxistrative controls shall be in place to prevent any load not rigged ia compliance witJx ehe criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks, received by T/S 3/4.9.7, disengaged.

2.D Ph ical Protect:'o The licensee shall fully implement aad maintain in effect all provisions of the Commission-approved physical security, guard traiaiag and cgxa1if ication, aad safeguards contingency pLans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Recpxixements revisions to 10 CFR 73.SS (SI. FR 278I.7 aad 27822) and to the authority of 10 CFR 50.90 and I.O CFR S0.54(p) . The plans, which contain Safeguards Xnformation protect:ed under I.O CFR 73.21, are entitled: "Donald Amendment: C. Cook Nuclear Elane security Elan," with revisions submitted No. 122 through July 2I., 1988; "Donald C. Cook Nuclear Plane Traiaiag aad Qualificatioa Plan," wax revisions submitted through December 18, 1986; and "Donald C. Cook Ntxclear. Plant Saft~rds Contingency Plan," with revisi.ons submitted through June 10, 1988. Changes made ia accordance with 10 CFR 73.55 sha11 be implemeaeed in accordance with the schedule see forth therein.

)~

Xndiana Michigan Po<<< C<~an~ shall implement aad maiaeain, in effece, all provisions of the approved Fire Proeeceioa Program as described ia the

'pdated. Safeev Analysis Report for the facility and as approved ia ehe SEE.

~ 4+~<) Z~e 4, 1979, sub]eca co the Eollowing provfs1on-The liceasee may'ake changes eo the approved fire protection, program without- prior approval of the Commission only if those changes would aoe adversely affect the abi.liey eo achieve and maiaeain safe shutdown ia event of a fire.

950628070'P 950620 PDR ADOCK 05000315 P PDR

GCO 0 2'C'~O 3/4.2.I. AERY PLUX DIFFERENCEo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ o ~ ooo ~ ~ ooo ~ 3/4 2-1 3/4.2.2 HEAT FLUX HOT QQQlNEL FACTOR...... 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT QQSNIH. FACTOR.. 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO.. ~ \~~~0~ ~ ~ ~ 0 ~ ~ ~ I~ ~ ~ ~ ~ 3/4 2-11 3/4.2.5 DNB PARAMETERS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 2-13 3/4.2.6 AZXAL POWER LEVELo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ 3/4 2>>15 3/4.3.I. REACTOR TRXP SYSTEM INSTNM2KhTION. 3/4 3-1 3/4.3.2 ENGINEERED SAH'.TY FEATURE ACTtJATION SYSTEM

, INSTRUMENTATXONe ~ o ~ ~ ~ o ~ ~ i ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ i o o o ~ ~ i o' 3/4 3-15 3/4. 3. 3 MONITORING INSTRUMENTATXON Radiarion Monk.coring Insrrumenrarion................... 3/4 3-35 Movable Incore Derecrors............... 3/4 3-39 Seismic Xnsrnunenrarion..............................-- 3/4 3-40 Mereorological Insrrumenearion. 3/4 3-43 Remorse Shutdown Xnstrumenearion.................... ~ - ~- 3/4 3-46 Fire Dere Pose-Accidenc Insrrumenearion..... 3/4 3-54 Explosive Gas Moniroring Insrrumenracion. 3/4 3-57 0 COO 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCUITION Scarrup and Power Operation 3/4 4-1 COOK NUCLEAR PLANT - UNIT 1 AMENDMENT ZO. m, ~, 189

(Continued) 3/4.7. SUFFRESSXON SYSTEMS Fire S sion Parer Sysaea............... ~ ~ ~ 0 ~ ~ ~ ~ 3/4 7-33 Spray and/or Sp Syscems.... ~ ~ 0 0 ~ 1 ~ 0

~ ~ ~ 0 ~ 0 ~ ~ 0 ~ \ 3/4 7-36 Low Pressure CO Sys . ~ ~ 0 ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 7-40 Halon Syscemi ~ ~ ~ ~ 00000 ~ ~ ~ 000 ~ ~ ~ 0 00 0 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ 3/4 7-42 F ir se S @casions ~ ~ ~ ~ 0 ~ 0 0 ~ 0. 0 ~ ~ 0 0 0 0 ~ ~ ~ ~ 0 ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 7-43 3 /4 FIRE RATED ASSEMBLIES ~ 0 0 ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ 0 0 0 ~ 0 0 ~ ~ ~ 0 ~ 0 0 ~ ~ 0 0 0 ~ ~ 0 -45 i 3/4.801 A.C. SOURCES Operating.... ~ ~ ~ ~ 1 ~ ~ ~ 1 01 ~ 0 ~ ~ ~ ~ ~ ~ ~ 0 0 0 ~ ~ ~ 0 ~ 0 i ~ 1 ~ 0 ~ 0 ~ ~ ~ ~ 1 ~ 3/4 S, I.

r Shu CdORlo ~ 0 0>> ~ ~ ~ ~ 0 0 0 0 ~ 0 0 0 ~ ~ ~ 0 ~ ~ 10 ~ g 0 ~ ~ ~ 0 ~ 1' 0 0 0 0~

3/ 8 9

'/4

~ ~ ~ 0 ~ 0 r

3/4 . 8.2'QNSXTE POQER DISTRIBUTION SYSTEMS ".

~ ~

A C..Dis~nx&on - Operating..'.;.. 00 ~ of 0010 & 10

. A.C.. Dismibuakon . Shutdown...:.... ~ 0 1 ~ ~' ~ q ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ >>( ~ ora r~

r D. C; . Dis~bucion - .OperacQxg;. ..'.

~

'.D.C. DisMbucLon - Shucdocm....;., 0 ~ 0 \ 0 ~ ~ 0 \ ~ ~ 1 ~ >> ~ ~ ~ 3/4 $ -16 "D.C. Discriburionperating - Train,N Saucery'ystem. 3/4 8 17 3/4.8.3 Co %R SOURCES 1 ~ 0 0 ~ 1 'q ~ 1 ~,'0 ~ ~ ~ 1 ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ 3/4 8-20 G 0 S

. 3/4. 9.I. BORON CONCENXIBLTXON:........- ~ >>~ ~ 0 \~ ~ ~ ~ 0 ~ ~ ~ ~ ~ 0 ~ ~ ~

3/4 9-1 3/4: 9. 2. ' XNSTRWENTATXON. ~ >> ~ ~ ~ ~ ~ \0~ ~ ~ ~ P ~ ~ ~ ~ ~ ~ 3/4 9-2 3/4. 9. 3'DECAY TXHE....... . -.-

~ 0 0 ~ 1 1 Q ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ~ 3/4 9-3 3/4. 9. 4 CONKQNMEHT BUILDING PEN%RATIONS .. 1 ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 9-4 3/4. 9. 5 COMMUNICATIONS..;....;;.......... ~ 0 ~ 0 0 ~ ~ 0 ~ ~ ~ ~ ~ ~ 3/4 9-S ~

COOK NUCLEAR PLANT - UNXT 1 AMENDMENT NO.

373

RUHR

~C~O 3 4 (continued) 3/4o7.8 HYDRAULIC SNUBBERS.................................... B 3/4 7-Sa 0 N SYSTEMS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ o ~ ~ ~ o ~ ~

(

3/4.7.10 FEZ RA 9 4 8 ~ ~ ~ ~ o ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ oo ~ ~ ~ o ~ ~ oo B 3/4 8 r

3/4. 9. 1 BORON CONCENTRATION.. B 3/4 9-1 3/4.9.2 XNSTRUMEHTATIONo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ o o o ~ ~ B 3/4 9-1 3/4o9.3 DECAY TIME. B 3/4 9-1 3/4.9.4 COHTAIHMJ2FZ BUZLDING PEHETRATXONS....................- B 3/4 9>>1 3/4.9.5 COMMtJNICATXONS.. B 3/4 9-1 3/4.9o6 MANIPULATOR CRANE OPERAB ILXTYo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ o o B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT HJEL STORAGE BUILDING............ B 3/4 9-2 3/4.9.8 RESXDUAL HEAT REMOVAL AHD COOLANT CXRCULATION......... B 3/4 9-2 3/4o9.9 CONTAINMENT PURGE AND EKHAUST ISOLATZON SYSTEM........ B 3/4 9-2 3/4o9.10 and 3/4.9. 11 WATER LEVEL-REACTOR VESSEL AND STORAGE POOL o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 9-3 3/4.9.12 STORAGE POOL VENTILATION SYSTEM. B 3/4 9-3 3/4.9.13 SPENT HJEL CASK MOVEMEHT.......... B 3/4 9-4 3/4.9o14 SPENT HJEL CASK DROP PROTECTION SYSTEM................ B 3/4 9-4 3/4.9.15 STORAGE POOL BORON CONCENTRATION. B 3/4 9-4 3/4o10.1 SHUTDOWN MARGXN.......... B 3/4 10-1 3/4. 10. 2 GROUP HEIGHT, INSERTXON AHD POWER DXSTRXBUTXON LIMITS. B 3/4 10-1 COOK NUCLEAR PLANT - UNIT 1 XXZI AMENDMENT NO. Qk, 4QO, ~, 189,.

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ZEST RIMRTkTXOH PERE DETECTXON XNSTR~hTZON C COHDXTXON FOR OPRLhTXON 3.3. 7 ks a miaheum, the fire detectioa Qxstrumentatioa for each fix detec scme shown in Table 3.3-10 shall be OPERkBIE.

kPPLXCkB: Nteaever equipmeat protected by the fixe de system(s) is equired to be OPERABLE.

kCTZOS:

Qhea the number of ERkBLE fixd detectors is less than the minimum number of required OPERkBLE tectors given below:

ao Rhea any, but more than one-half the otal or no two adfacen&

ia aay fire detec sone, Function X, etector(s) located-ontside of ccmta

1) restore the snop t leshowa in Table/3.3 10 axe inoperable:

detector{yf to OPERkBXZ status within'4 day', 2) after the 14 y time LMt acpixes, within the. next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish aa hour+ fixe watch patrol to inspect the sone(s) vf.th the inoperable detector(s .

b. For inoperable detectors locat outside contaiameat, within 1 hna.

eecablksh aa hoazly firs~rch gcml ra inayacc rha caaa(a) vhsa:

1) moxa than one-half detectioa tone showa g the Punc~ k, fixe detectors ia Table 3.3.15 axe inoperable, or 2)

~~ fixe Function B mme det ctors shown ia Table 3.3.10 are inoperable. or Co are inoperable. j l

3) aay two or mor. ad)scent fixe detectors+ shown in Table 3.3.10 For detecto s) l.ocated inside containmeat: 2g establish a fixe watch patrpL to inspect the containmeat xone ab least ance per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, oy 2) monitor the containment air temperature at least once per hone at the locations Listed in Specification .6.1.5.

d. The provisions of Specifications 3.0.3 applicable.

and 3.0.4 are c l

~hd]aceat fi-'e detectors is defined as any detectors physically adjacent in the fi e detec ion cone.

COOK NUC~~ Pi~ - UHXT l 3/4 '3-51 MAID~ NO- 79>

0 IHSTRUHENThTZOH SURVEZLXhHCE RE UXREtKHTS 4.3.3.T The f&a detection system for each fire detection xone ihovn in fahla 3.3 10 shall 5'~stotstvstsd OPEM1E as follovs.

d s3.3.7.1 Eath of ths dstsotoss Pt tha shoat taqtjtsd fft dataotfot sfatsts vhfoh ats aooassfhla dotitt pivot opststfot shall +dfaotsttatad OPERkBPE st least once per montha by perfoanance of a CHhHHEX, PUHCTZOQL TEST. Pire 6

detectora vhich. are not acceaaible during pLane operation shall be demonatrated OPERJSXE by th>> performanc~of a CEhHHEX, PUHCTXOHkL TEST during each CO@ SHUTNQl exceeding 24 heWunleaa performed in the previoua 6 monthas 4.3.3.T.Z The aupe detector alarm circuita for the above".required fire detection system be demonstrated OPEMXZ at leaat once per ~tha.

The auperviaed detector alaaa circuita include the detector circuits, fire and trouble"alarm circuf.ta from the aueote fire protection control panel ta.

the Conirol Room emergency fire control panel. and audible fire and trouble alan@ circuita s

~

COOK NUC~~ FLAT - UNIT 1 3/4 3-52 ~~mrs NO 79,530

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g a):-levee'an DT 'I 23/OC b) c~ evac&nXSST SS/QC c) c'emc an 609 41/OC F~eva- an VL cL) e) ~e~~

~) Hew ."nel lST 4L/QC 34/OC P+Z L'-ea 4/OC g) RP Access CanaeoZ;4 Chem ~s ZS/0 Esca Scum V?J.ve = clasn=e le ~~ Sne?m L' 8=ca gg/Q~

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3/4 3-53 Au. fuji. iO ~

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(Coae&azed)

Hem ZEST+

(x/y)+ (x/y)+

IG. Cab~>meals

<<) Quad X, Cable Tamil 0/3 0/4 b) Quad 2 CabLe Tunnel 0/4 0/7 c) Quad 3H 0/4 d) Quad 3S 0/3 e) Quad 35 y 0/3 0/4 quadr 0/6 UX Chaa~a1 PG.zer Venrila&oa Unics

<<) 1-HV-AES-L b) 1-HV-AES 2 0Q~

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c) 1-HV-hCRF 0/L~~

d) 1-HV e)

CX 1-HV-CPR X 0/L~

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f). L2-HV AE 0/L~~

'U1 Coa a) RCP 1 L/4 b)'RCP 2 c) RCP 3 d) RCP 4 e) Cable Trays $ 8/QHtw&04~

Sys=em procacm area common co boch Unics X and 2 x is er of Puncheon 4 (early warning f'"e dececMoa and noc~ icacioa only) ins~enns ~

I y is~ber of Puncheon 3 (acazacioa of f~"e expression sysaans and early warning and nociftcacion) ias~eacs.

g~~LXy iascaLXed ca asaama&caLLy delugeycharcoal however, manuaL actions are aow necessary.

fi1~.

aoc re~ecf co be OPHUUKZ hxcixqg the perforsance of Type h Coarainmear Leakage Race @earn.

The~iscars ara locacecL vichin cable erays which concha combus~la cables, ia boch upper end Lower concaizm~n rhroughoun cpuLdrancs L 4.

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4.7.9 ~ -1 The fire suppression vater syscem shaLL be demonstrated 0 ao c least once per 7 days by verifying the vacer supply e fire vater tanks.

~1 d once operating per 31 days on a STAGGER TEST 3hSXS it for ac least 15 minutes an r circulation SLav.

starting each pump Co ~ lease ce per 31 days by verifying that ed. or autamatiA:) in the flov pa valve (mamxaL, that is noc locked, paver ap sealed, ar o earise secured in position, in i.cs correct posi,tiAnL.

de least ance per months by per"o e of a system flush of above gramui internal dKs Xbutf.on headers d fire hydrants.

e. kc lease ance per L2 chs by g each cestable valve in che flov path thraugh ac 1 c ane l,ste cycle of fuLL travel.

"'r kc least ance per 18 monchs performing a syscem funccionaL test vMch includes simulated a cic actuate of the syscem throughout its operating e ce, and:

VcaMying that e automa valve in the fL'ov pach actuates'

. co its catrecc osi,cion,

2. Ve'rifying t each pump develops flov of at lease 2500 gpm t

3; ~

ac a syst N

head of at least 300 fe

.-.three po ts (mimi@, rated,. and 'pe ) 'an the-pump's p~ ce curve~ '. " ~

g'ach:vaLve in the flov path-chit'ot testable during

~ ....

of vacer sty'bsmriag

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c .operas'hr'ough'st 'leaic:one comp).e cycl'e'. of fuL1 ',p

, 'end P

'Verifying 'that each pump. starts in i,ts preplanne secpxence to

'aihtain che fire suppress'ater system pressure. eacer

."than or equal to 100 psig.,

hc Least once per 3 years by per-arming a seri.es of Slav tests o that mery fire main segment (exoluding individuaL system suppl9. )

~ has been verified co be'lear of obstruction by a fuLL:flov cesc.

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coom Hacrzaa r~ - azn'-r 3/4 7- 34 dHEHDHEHT NO.

173

~ I 4a44 4

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I C c ad 4.7.9 .2 The fixe pump diesel engines shall be demonscxaced 0

a. kc lease once pax 3l days by vextfying:

The fnaL scoxage csnks concain ac lease 160 ons of fnaL, ancL 20 diasels scaxc fxom ambianc condi 1 30 minncas.

b. Lc lease paz 92 days by vexifying c a sampLe of dieseL fnel fxom che fneL coxage csnks obcahxed accocdsnce vich hSTg-D4Q57-SI. is vichin ch accapcabla Umics ecified Qx Table 1 of ASTK-D975>>81 when che d fox icosi, vacax'nd sedimanc.

c. Ae lease once pax 18 chs by sub]eccing che diasals co an inspeccion hx accoxdanM vi pxocadnxas pxapaxecL in confmxccion vich che msnnfacccxex's xa dacions fox chis class of scandby s alice.

t 4.7.9.1.3 The fixe pamp diesel scaxcing accaxy banks and chaxgaxs shaLL be deaoxxacaaced'PShLBXZ:

~

Ac lease once p 7 days. by r~.at:

I ~

l. The elec lyce'evel of each bac xy is abide che places, .

. 2. The baccaxy volcage of eaqh is 'gxaacax thur 24 00l, b...,

'ht..

a 1, once pex 92.days

~ a pxiac'a. for concixrued by'~iQ~g s~ce

~

waif chac. aha each bac"a .

pacific gxaMcy

~ c. ~

least once pax 1S monchs by'exifyfaxg chac:

3... The baccexias, ceL3. places <<Lnd baccexy packs shov vt:~LL Qxdicacion of physical damage ox abnoimLL <<Lacaxioxac on, and

2. The baccexy-co-baccaxy end caxm~LL ccnmeccions axe c3.e cighc, fxae of:coxxosion,'nd 'coacad: vich anci-coxxosion mac axial, I

COOK mcrZax paar - UHIT 1 3/4 7-3S ~mrx No. m, ~.

173

~ l g~

3.7.9.2 3.7-5k The spray ~or 3.7-5B shaIl spciakLer systems be OPHM3LZ:

located in the areas in Tables whenever equipmenc in the spray/spr&dcler pro cced area is re~ed co OPERh1KZ.

hEXM'-

Vith one r more of che water spray as lisced in Table 3.7-5h, inoperable, within 1 hour: 1) verify che decoction syscem for the affected cracion unit is 0 per Specificacion 4.3.3.7, or 2) escablis a concinnous fire pacro1.+

Pith one or more the sprhd6e systems as Mted in Table 3.7-5B inoperable. within hour: 1) v rify thac ac. lease one of the dececcion syscems, re pr d (eleccrf,c per Specification 4.3.3.7 or pneumacic per Tab1e .'7- ), for the affecced area is OPEM3LE and establish an hourly fire cch patrol, or 2) establish a concQxuous fire watch patrol.~

The provisions of Sp ica ns 3.0.3 and 3.0.4.are noc applicable.

~ ~ ~

or high adiacion areas, peri'odic'.monicoring'and .hour3.y. logging) of osed circuic te3,evtsion coverage is an accepcable substitute for a con~ us .

fire watch. Por high radiation areaa where closed circuit television cove a

.-'does, nac cacisc, aa hourly fire wacch patrol will be inscicnced.

COOK NUC~~ PLhNT - GHZT 1 ~ '

3/47-38

4.7..2 Each of the above required vacer spray and/or spzInkler syscems s be d craced co be OPKEASIZ:

dc I.ease once per 12 monchs by cycling each cescabI.e mr pach chrotqga ac I.ease one complece cycle of &all mt'he as ~

ded by Tech'.caI. Specificacion 4.7.9.1.1.e.

b. kc 1 c once per IA monchs:

ocnChqg a syscem funocional case vhi includes s~xlaced cic. accuacion of che syscem, and:

Ve chac che aucomacic es Qx che &mr pach aocua e co cheir correcc posi on a case signal, and b) Cyc1ing ch valve in che cd pach chac is uoc cescabI.e during p operacion ough ac lease one complece cycle of full I.. 1+

2. Sy ~Q, inspeccion f uge and preaccion syscem piping

. (chis is noc required . syscems slxpervtsed by air) co verify

. cheer incegricy.

3. Ey visual'nspec chac there M no lockage.

of open head deluge coracle co ~jr

'kc; X,ease ance per .years by perfo g.an air Q.mr case chrough. che.

piping of each en'head deluge'yscem and ve~~g:each open head .

~

'eluge nqcsle unobscrncced.I P

1

\

'The f ~ I.ecion proceccQm vacer flmr surveillance cescing, may be of che '5ge suspend uncil.

.che proceccicn vacer scorage'ank and fire

. ins

. of '

cions amendmenc ~

(Hay-.31, I.993) . The sarveiXlance tescing suspended is a esuI.c he iniciaced ac.jcs normaI. frequency'vichtn four onchs che nev fire.proceccion vacer scorage canks and fMe pumps being decl d OPERATE, vich che exoepcion of. unic oucage required cescing vhich vould 'be compZ.eced before che end .of che nexc schedu1.ed unic oucage; COOK NUCZZhR, 3/0 7-

1-PT- -1 Charcoal FQacs HNQRl E1ec~c eag 1-HV-AES - Charcoal Filets Haul - E1 Heat 1-iP-ACRP-1 EmuaL - E1 - Heat L-N-CPR-1 a1 &lcecs HeuuQ. - eccric - Heac 12-Fl-AZK Charcoal Qr~

1-HV-CXPX Charcoal, F ears - Eleccrh - Heac

~

~ 0 shared syscma oaf.rh Unic 2.

COOK NUCLEAR PXd&X - UNIT 1 ~/lr 1-38 AHENnmrf NO. ~. -:

building Preacrtoa Sprinkler Dry PG.o El. 587 fc.<</<<<<<<(Nor!nally acce a&le areas, charging and S eely Xafecrf.oa Pump Rooms, S73 and rai~

09) co El.

Aced,diary b ding Preac&oa Sprfakler El. fc. (Eormally 609 accessible Pump area, ar, s

CCF ays uo EI,. 633 ancL 62Q ave Chem. Lab)

Auxf,liary builcKag er Dry Pilor<<cc E1. 633 fr.<</<<<<<<(Ho I.y accessible areas, excL HVAC Vescibule Areas aad sraf,~ays co El. 650)

Auxiliary Feechrarer Pump Auro matc Corr f,dor<</<<<<<<

~

Turbine BuiI4iag,'El; 591.. ' c'ipe

., Ceaeracor'ncL (ExceadecL eo Dimal

~

'eaeracor Co~der<<<<<<)

A!nci,lory BtdkcKng ':. Preac&o Sprintcler, Dry Piloc<<<< '.

<</~

~

HancLling .Area . (Sl- 09) er: . Dry'ild~

I liary Buildia 'reacrioa 1

bruc!!c!cing ' Sp (El 5') /<<<<<<

Reacror Coo c Pumps (4)~ Preacrioa Spriatcl '~cl Coarracror Access Coa~l Vec.'Piwe abc Building El. 6l2)

S rem proceccs area co!!!mon to'och Uairs l and 2.

Dry. Piloc Acuuacion is:considered co.be a heac'acruaceC pneumat. ~e ~

deteccion sysrem.

Locaced ia areas which also here aa aucomacic decagon sysrAu!!.

CMK NUC~ 2LANT - UH1T g j

~ >/4 >-! ~~

t23 HO. 4$ , ~

C

3.7.9.3 The low pressure CO2 systems located in the areas showa Table 3.7-6 s 1 be OPERABLE.

Meander equipmeac in the low pressure C02 pr'o cced areas is required to b OPERABLE.

hQXlQH-Qf.th oa or more of che above required 1 pressure CO syscems isolaced om aucomacic operation for pe oanel protection, verify thee ac le c one zone of fire dececci for che affected area is OPERABLE per pecificacion 4e3.3.7 in rder co permic encxy for rouciae tours, maintenance, cons on, or surveillance cescing,

b. With one or aors f the retained spstens shown in Table 3.7-6 at least fire

'r inoperablawi,thin hoar: 1) w one tone of deoeonion for tho eared ere is OPEE631E per Epaoifisation 4.3.3.7, and esceblis a fire ecch petrol co iaspecc the effected fire area once per ho ) Establish a continuous fire watch co pacrol the affected

c. The provisions of Spec ons 3i0.3 and 3.0.4..are aon eppU.cable.

ZL-3 4.7.9.3 Each of the above equQ:ed low pres e CO2 systems.shall .be demonstrated OPERABLE:

a.'.

~

Ac 1'east on per-7 days.by'vex'1fyiag the CO2 .storage'caak. level co be gree r than ~r equal,'ta 50%'and '

essure to Be greater chan or'quaL 285 ysig,', ".and . ~

. ~

' ~

b.'c 'he le ow oace per 31 days by path is in .the verifying tha correct position. ~

each manual valve in eesc once'per 18 moachs by verifyihg:

The syscem valves, associaced vencilacion ers and fans, encl self-closiag. fire doors operace eucomaci

receipc. of. a simulaced actuation sigaa3.,

lly upon and

2. System actuation methods l,'aucomacic. from 'dececcio 'ystem, .

m'anual pushbuccoa scacion, 'aamL1 pneumatic 'release are.

cesced to verify proper accuacion of the system.

3. Plow from each nozzle during performance of an airflow.o CO "Puff Test".

2

~

e COOK NUCLEAR PLANT - UNXT 1 3'-7-.40- "-""-=""- ~mm No. ~,

~73,

ERR~K '.

Diesel Generacor 3hB Room Cams flood Hs4c Diesel Generaco lCD Room Cross-amact Esaa Diesel Gene~car Fuel Oil Pump Room

. 4 KIT SMcchgear Rooms EaaaaX, Conc ol Rod Drive, Traasf. Svitchgear Rooms

/ Hamal Eagineered Safety Saticchgear om manual Svicchgear Room Cable Vault Cross-coned Ionization and Xnf=ared Auxiliary Cable Vaulc Ionization Caac=ol Raaa Cable VaMc (Baakup)+ HaxaaaL Penes-anion Cable Tunne'X Quadrant L Hematal Peaec=action Cable l Quadrant 2 Eazaml Penec=acioa CabXe Tunnel Quadrant 3N Penes=ac on. Cable Tunnel Quadraas 3H Penecraci'on Cable Tuanel Quadrant 3S Penec=ac'on Cable Tunnel Quadrant 4 I

l

'Conc=oi. Room Cable Vault CO~ System is only required co be operable >hen the Cable Vault Halon System is inoperable.

I COOK HUCL='K .LANT - 7LtiT l 3/4 7-41

.r

3.7.9. The Halon system locaced M che Control Room Cable Vault be.

OP whenever equi.pmeac in the Halon procecced ar is required co be OP With e Halon System isolated from tic operation for persoan protection, verify chat ac le c one xone of fire dececcio for che affected area is LE in order co permi.c encry into e cable vault.

b. Qich che above required Halon iaoperable, within 1 hour:

1) verify thac lease one ro of the fire dececcioa system aad che backup CO fire suppr sion system for che affecced area are OPERABLE per 3p cifica 4.3.3.7 sad 4.7,9.3 respectively, or 2) cab h a conciauous fire vacch patrol.

c The provisions of Spe cions 3.0.3 aad 3.0.4 are aoc appli.cable.

4.7.%.4 The 'a&eve acquired on system shaL1 be demoasc=aced OPERABIZ:

a. '. Ac least oac per 6.moachs by veri!kg each Halon scorage'

'co be grea r, ch'aa or equal to.954 of . charge veighc or r~

appropria of fuli U.quid level, aad co be ge pressure corrected'or'ment ger than or equal co temperachze".

90%

r ~ ~ ~

b. it: le c oace, per..'18'onths by:

~ r

1. '- Verifying the system (includiag associaced veacilaciori

'dampers.and fans, sad doors) is tested for p oper operation by 'a simulaced accuacioa si,gnal; ~

~ \

2. System accuacioa methods (automatic from decec& system, manual pushbuccoa station, and manual cyL'Quier ac car)

.'re co.be tested co verify proper.accuacioa of the cern.

';',

I Performance of an air Q:ow cast or CO2 puff.case through headers'rid'aorrles to assure that chere is.no blockage.

r'OOK NU - UNXT 1 3/4 7-42

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hDMZHZS'i'.- VE CONTROLS

b. Ac Least one Licensed Operator shall be in ke conmL mrna vhen eel is fn the eactor. Xn addition, vhile the cnic Ls ~~ Mode L,

2. 3, or 4, ac Lease one Licensed Senior Operacor shaU. be in 4e con~1. room.

Co ~ indiMdcal ~'"fed in radiation protection procechx-es shall, be on site vhen cd. is fn the reactor.

d. XXX, CQRZ AIZKLAXXQHS shall be direccI.y sapervtsed by a Licensed Senior Operator ~ed or qzaLigied in refceUxxg and CORE htZRCXOMS (SQ-4) vho has no ocher concc=enc responsibiI ~ties g this operation.

eo ~'"e br'Sade of at Least S members shall be onsice ac al3. c e fi e bri a clcde 3 members of che minima shift t=

or axxy pars e~ed for ocher

~or sage shntdovn essen c~if~my the cni a

Th ~ amount of over~ voted by plant scag memhe s Per otninC safety-related cnotions inst be Mead 'a accordance vi4 HRC.

2o1,'oy Scacenenc on voting boors (Cene~c ~atter 8X-D) ~

e Shi>>= Sup~or, kssistsxxc Shig Sap~or. and Uni Supervisor shall hold a Senior Operator L'oense-The Operac~~ Soper~endent inst hold or ha~ held a Senior Operator I'cense ac Cook Haclear 2Lanc or a s~M~a reacm r axxd one i

d-Le~1 Operations 2~mdcc~~ Supe~or shaLX hoI.d a cn=ent Senior Operator L'cense.

t 7 M ~~p~c~d < v+~N<~~ ~c ~ ~i toot o C'i cccL uc4 'ia a Xc:s'a4 l

'/

~

hoes.r 5'

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C- ~ o>-5'iW a/ )c a (cPOQ pcu i'sJccs FC ocJ p<o~Qox pro Cedcrrg5 c s, P~y~ j ~~/' ~v'p~ l ~ lat~Jr n.c,~r ~ I~ &8M~ ~ 6 // ~y~ J Ia' ~ r +J

=ha~ccicacciasL cpacL'~LocL cm =scLLss~c passos=~

aaapasL wa saba ~ic for a perwd of ~we aoc a) axe',.

facie a~s. Loss

~

M 4s ~ccacrsfqc>>

~ A paaascia=as accommodate aacL We asoaas taTeneoced abs provided mediate ao-m4 ~~, aJcea a ~~c!xe rahu -ad CQOC HOCKS 2~i - mÃi I. 6 X hZKR~ ZO.py gag sgZ

6.8.L written procedures shall be established, implemenced and maintained covering che accivities referenced belov:

a. We applicable procedures recommended in Appends A of Regulatory Guide 1.33, Rev. 2, February 1978.

b De1eted.

c. De1eted.

d. PROCESS CONTROL PROCRAM implementation.

e- OFFSITE DOSE CALCULATION jQKJhL implemeatati.on.

f. ~lity Assurance Program for effluent and environmental monicoring using the guidance in Regulatory Cuide 1.21, Rev. 1, June 1974, and Regulatory Cuide 4.1, Rev. 1, April 1975.

6.8;2 Each procedure and administrative policy of Specification 6.8.1

'above,.and changes thereto, including temporary changes, shall be revieved prior to implementation as sec forch ia Specificacion 6'.5 above.

6.8.3 A plant program fox'ost-accident sampliag shall be escablished, implemented, and maincained which vQ1 ensure the capabilicy co obtain and analyre raaccor coolant samples, concainmenc atmosphere noble gas samples., aad uaic. vent gaseous effluent samples for iodines and particulaces uader accideac conditions. The program vill include the follovtag:

Training of personnel, b Procedures for sampling. and analysis, e Provisions for maiatenance of sampling and analysis equipmenc.

i pp*C+rod pro~ p~~ i ep IC?~y*4 oN COCK NUCLEAR PLPQT7 - UNIT 1 6-13 ANENDNENT NO. ~, 444 192

The OP~XLITY of the remoce shucdovn instrumentation ensures that sufficient oapabiLity is avaiLable to permit shncdovn and maintenance of HOT SXLÃlBY of che facility f~ locations outside of the coal room. This capability is re~ed in the event control room habitability is lost and is consistent vith CenezaX Design ~teria 19 of X0 CHL 50.

The OPK4LSXLZTY of the hppendhc E remote shutdovn instrumentation ensures chat sufficient ins~ncacion is available co permit.~hucdovn of the fac-'Lity to CKD KGJXDOQN conditions at the Local shutdovn indication gSZ) paneL. Zn che eve of a fire, normaL pover to the LSZ panels may be lose. hs a result, oapabiLicy co repair the LSX panels f om Unit 2 has been provided.

alternace povez supply is not available, fire vacches vtXX be escab1.ished in Xf the those fire areas vheze loss of normal pover to che LSX panels could ooouz in che evenc of Q.re. This vtXX consist of either establishing continuous fize vatches oz ~erS "ying OPERABXLZTY of fire detectors per Specification 4.3.3.7 and establishing hourly-fire vacches. The details of hov these Qre vacches are to be Qaplemenced are included in a plant procedure.

7 f.

OP GAB -- of the g e detection .systems/deceocors ensures t ade~ce detec ion oap ~ is available for the cspahillcy ls ca~esses cc decec ecd prompt detec lecace of fires. This s Qx aheM assi@ scages.

o ompc detection of the vill reduce ocentiaX for damage to safety related sysc~ oz componencs in ' of the specified systems and is an integ a1, element in the overall proceccion program. Zn the eve..'

chat a portion of the f~-e ction systems af era&le, Ce hGTZOH scacements prodded maintain the licy's fi"e protect'on pro allovs for con~ed operation of th Xi~ unt'l the Moperable system(s)/dace are restored to OPUAB . Hovever, ic w< not ouz intent co re1y upon the ensacory acti or an extended period of mme and action vill be taken to resto e numbe of detectors co OP~LBL= "scacm vithin a reasonable pez'od.

The OP~XLXTY of che post-accident ins~ntation ensures that sufficient information is available an selected plant parameters to monitor and assess these variables durga and follovtng an accident.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. The method for decerndning the next incerva1 for the visual inspection of snubbers is provided based upon che number of unacceptable snubbers found during the previous inspection, che category size for each snubber type, and the previous inspection interval pex'RC Generic Letter 90-09. A snubber is considered unacceptable fails co satisfy the acceptance criteria of the visual inspection. Any if ic inspeccion whose results required a shorcer inspection interval will override the previous schedule.

When che cause of the re5eccion of a snubbex; is clearly escablished and remedied for that snubber and for any ocher snubbers that may be genericaI.ly susceptible, and verified by inservice functional. cescing, thac snubber may be exempced from being counted as inoperable. Generically suscepcible snubbers are those which are of a specific maha or model and have che same design feacures directly relaced co rejection of the snubber by visual inspection, or are similarly Located or exposed to the sama environmental conditions such as temperacux'e, racLiacion, and vibracion.

When a snubber is found inoperable, an engineering evaluation is performed, in addition to the decexminacion 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 sha11 determine whether or noc the snubber mode of failure has imparted a significant effect or degradacion on the supported componenc or system To provide assurance of snubber funocional reliability, a represencacive sample of the installed snubbers will be functionally tested during plant shucdowns ac'24 month incervals. Observed failures of these sample snubbers shalI, require functional tescing of addi,cional unics.

The service Life of a snubber is evaluaced via manufacturer's input and information through consideration of the snubber service conditi'ons and associated inscallacion and maintenance records (newLy installed snubber, seal replaced, 'spring replaced, in high radiacion area, in high temperature area, ecc...). The requirement to monitor the snubber service Life is included co ensure thac the snubbers periodically undergo a perfoxmance-evaLuacion in view of their age and operating conditions. These records wi11 provide scaciscical bases for fucure consideration of snubbex'ervice Life. The requiremencs for the maintenance of records and the life review axe noc incended to affect plant operacion. snubbex'ervice The number of snubbers co be functionally tested during each surveiI.lance is based on calculacions perfoxmed co allow excension of che surveiLLance incexval from LS months to 24 monchs, and therefore, the number of snubbers functionally tested deviaces from the number required by the Westinghouse Standard Technical Specifioacions (NUREG-0452, Revision 4) .

A.lisc of individual snubbers with detailed information of snubber Locacion and size and of system affected shall be available ac the plane'in accordance with Section 50.7L(c) of LO CFR Part 50. The accessibi.Licy of each snubber shaLL be determined and approved by the Plant Nuclear Safety Review Committee. The determination shalL be based upon the exist'ng COOK NUCLM PMT - UNIT L 5 3/4 7-6 ALLWDXENT NO. ~, ~ 1~

e t4ou& 5 >)0 7-4~

radiation Levals and the expec"sd t~e to per orm a visuaL Lnspec~ in each snubber Loca~n as well as other factors associated with accsssibili du-'g plant operamns (e.g., temperature, atmosphere, Locadhm, etc. ), ancL recommendations of Regulatory Cuides 8 8 and 8.LO. The addition or deletion of any snubber shaLL be made in ~rdance with Secern SD.59 of XO CZR Pa=

sa-4.1. S 0 S The ~~TX'f the f ~ suppression systems I

suppr in any sprinklers,,

'e ~

sion capability is available to confine of the facili~ ancL ensures ext~pzish where safety relatecL ecpIipmszzt is happression system coasts of the water Ealon ancL f' hose stations. The..collect~~ ility of that fi~ - '"g ancL/or the "'e sa ety-relatecL su procec ~ion program ssion systems pmenn and is is adecpxaue a ma)or element ~

to minimi=e ~eezztiM damage facility fi=e Za tte evert atet aae a~ation muse be isolat

'r formare ca rarprerriaty~ t reqti~~ atttma=-'a personal protection cv pe~t ezzt~ for routine toum, maintenance 'Xconst~c~n, g~ eiJ 'nce da~ in 'ze protec=ed a~a, the fi ~ de ion system( ~regni ed to be operable by S pecatwn 3.3.3-7 shalL be '. ~ied 4/5'a operable. ZsolaMn of an automat c CQ suppression system 'emporarily puts this System 111 a auiozI mo e Reliance on the fi=e detec~n r con)unction with the abili manuaLly cKscharge the CQ sion wiLL provide adezVIate ec='on or periods when p nnel are to work in these areas-Zn the ~en that por ' the <<~~ suppres' systems ara izzopez~ler alternate backup f~m fi wg epzipmenc is recLzIiM.~ be sade erailable t-'ze affec ecL areas unt +. e inooerabLe equipmezzc is re to segvtce-When ".e inoae~le. "~ fightmg ecpxi.pment is &tended for~ e a bacJozp of f'-e supp

..ate means o -e i.on, a Longe>> period of figh~g t~

than i~ the inoperable ec(ui is pr~~

al'Lte means "' suppression. 8ackup .' protsc~

hose static or near the area, or f'"e hoses ~tacL to the af ec"-

Bowe~e, perable por ~ns o f the fi ~~

~~ zzot our; intent to rely on backup systems or other compens an ex ended oerwcd of and ac~en wiLL suppression syst~ to CP~QK- sta=~

r r/. a reasonable period'- 1

QMRR 4 7.9 The surveillance requi~nts provide assurance that the a~m OPZItMZZ,~

requi~ents of the fire. suppression systems are met. While perfoaaing the surveillanees spec'~ied Ln 4.7.9.1 the fire suppression water systsm is s~3.

capable o f~erf orming its intended function. Consequently~ it is not necessary tv+enter the ~oN sTlLI"DCHT specified in 3 7P' while the SURVEXZXAN~ spec4$ 9.ed in 4.7.9.1.I, are heing per ormed, uxxless the tested equipment fails+the sQENEZZXANc . Zn addition, an allowance is made for ensuring a st icient volume of Halon and COI in the HaXon and C02 storage tanks by verMying ither the weight, level, or pressuaaraf the tanks-The fire suppression ter system has three fire pumps coamuxn to hach units which discharge into underground ring headers. ~There is one moto~iven horirontal cent ifugal f~ pump rated. at 2500 @gal thar. takes suction from the fire water storage 'ytanks 7 and two dkesel~gine~iven hori=ontal centrt ugal fire pumps rata@,at 2500 gpm thaty>take suction water storage tanks.

f~ the fire Having a combination of. diesel~ivsn and electric motor~iven pumps in the tern design is consistent with NRC Branch Technical Position APSCB 9.5-1.

The purpose of the charcoal filter~i~ suppression T/S is to account for detectioxx ancL suppression of fi es~kx. the charcoal filters~'anual operation of these systems is allowed hecau~ two-point heat detection wxth con~1, charcoal filters- The opKVLBgLITY of ~

room and local annunciation of trouble 'conditions is provided for the fi~ suppression system protec in

.,the charcoal filters ls. only'requj ed wheo there is charcoal in the filters.

Actuation of spray'water onto the ctxarcoalhfilters requi es both the manual opening of the system is ation valve and reaching the high temperature ala~

setpoinu for the aut c opening of the syst 'eluge valve Because of the ina~essibility of the lower contehunant to personnel during operat~xx due to radiation exposure concsrnsg the use of one or more CCTVs in the containment, to monitor 'or fX~ and smoke, is an acceptable sube6itute to an hourly fire watch, if the Qre suppression system hecomes inoperabI.e.

~

spec'ed I

All hourI.y"f'~ watch pat~is with a margin of f'en minutes.are per ormed at intervals of serg minutes continuous fire watch requi~s that a t~ed individual he ~~ thei.

area at a3J. ~es and that each f~ "e cone within the specified a-ea

e. patrolled at Least once every fi teen minutes. with a margin OMfive minutes.

BI/478 AMENDMENT Ng Wi ' 'i Re sed bv" C bette da ed Decem er 14, L994

3 4,7. C c ed

h. crol valve is defined as a valve that vhea closed does noc Leave aa .

ale ce open flov path eo a system. 4 seccionaliring valve M define a valve c vhen, closed does noc prevent an alternate open Q,ov path to syscem d hence does noc make the fixe suppression vaear system bl.e.

Under c ia sieuacioas, the closure of a seccionaliriag valve fo d by che closure specified sys f a second valve vill noc leave an open floe path to

. Xa this instance, Action Seacemenc c of Spec ication e of ehe 3.7.9.1 is app ble.

Eamual aceuacioa of 0 fixe suppression systems provides a quate fixe proceccion fox the ected areas based oa OPZRLBLE fixe ececeioa ia the area, Lcnr combuscible 1. diags, cnd prompc fire brigade sponse to Warms.

%my of ehe kecioa Scacemea take credie for 0 fixe detection ia Lien of a fixe vaech vhea a fire p ceceion syseem is arable. OPEBkSLE fixe dececeion provides sufficienc ly vaxniag capab ty of a fixe to the appropriace Concxol Room.

During Surveillance Tesciag of a Zur assur CO> System vith the system iaopexabi.e, the requiremenc for a coa fixe vacch may be suspended during poreions of the tesc vhich resulc may resul.c in a discharge into the CO> pxoeecced area. Similarly, aced eo have the Lmr P .assure CO> Sys if a CO 4 cion occurs vhich results tn ehe

.iaoper'able, the reqahemeac for ma a coac&zuous fixe vacch may be susp d. Xa iehex .case', the area ~eceed shaLL .be rescore'd to habicabiliey soon as cicable, 'after vhich the

~

coac&mzoaa fixe vaech. is to bo. r established & e system is still'inoperable.e.

347. 0 hS The'. OPKhLBXXZTT of the f e. barrier's an'd b~ex-peae~ easuxa".thae fixe

: .damag'e vill be Limited. These design fhaeures m~Me'the ssiMLi~ oC'a

'f

'iag1.e:fire.iave&tag re thaa one fixe.sxea'rior"to decec sad axafxxguishmenc. Th fire bakers aa4 fixe barrier pane~cion ealiag dances are period cally inspected to verify their OPELLBXLXTf, e funccioaal case the fi-e dampers is provided to ensure thac e dampers remain funcei I.. The ventilation seals.'area seals around vencila oa duce vork penecra g fire bar iers. Xe's noc our intent to "ely on bac syseems or ther compensacory measures for an extended period of time d accion be.taken to rescore the inoperable portions of the fixe race assembl to OPERABLE scacus viehia a reasonabl;e'eriod.

~ For e purpose"of determining OpZRABXLXTT>.in OpERhBXZ fixe raced assembly aa /or s'ealiag device's oae ehac M capabl.e of performiag its intended safe ccion.

COOK LEAR P - L 4 7-9 err N . ~ 171

Docket No. 316 Page 5 of 11 (l) Deleted by Amendment 63.

(m) Deleted by Amendment 19.

(n) Deleted by Amendment 28.

Amendment (o)

No. 12, 180 described in

've controls for fi oa as submittals dated January 31, 1 ~october 27, 1977 s and maintained.

l ~ngJemented Amendment Deleted by Amendment No. 64, 121 Indiana Michigan power'atapazlp shall implement and maintain; in effect~

all prmrlsions of, the approved Fixe Protection Program as described in the Updated Safety Analysis Report for the facility and as approved in the SEE Zune 4, 1979 ',.subject to the following provision:

The licen'see may image changes to the approved fixe protection program without prior approval of the Commission only if those changes would not maintain safe shutdown in the adversely affect the ability to achieve and event of a fire.

0 G CONDX 0 P 0 3 4 0 0 S 3/4.2.1 h3HAL FLUX DIFFERENCE 2-1 3/4.2.2 HEAT FLUX HOT QiANNEL FACTOR ...... 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT QiANNEL FACTOR ............ 3/4 2-9 3/4. 2.4 3/4. 2. 5 PARAMETERS'/4 QUADRANT POQER DNB TILT RATIO.............................. 3/4 2-13 MODE 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ 0 3/4 2-15 MODES 2, 3, 4 and 5 3/4 2-17 3/4.2.6 ALLO@ABLE POKE LK o ~ ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 2-19 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION . 3/4 3-1

'3/4. 3. 2 ~ ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATXON o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-14 3/4. 3. 3 MONXTORXNG INSIRUMENTATION Radiation Monitoring Xnstrumencation ................ -. 3/4 3-34 Movable Xncore Deteccors .............................. 3/4 3-38 Seismic Instrumentation ............. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ 3/4 3-38a Meteorological Xnstrumencation ...... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-39 Remote Shutdown Instrumentation ..... ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-G2 Post-Accident Xnscrumencacion . 3/4 3-4S ze Explosive Gas Monitoring Instrumentation............... 3/4 3-53 3/4 .3.4 TURBINE OVERSPEED PROTECTION. 3/4 3-56

4. 4 CO 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRGtKATION Startup and Power Operation . 3/4 4-1 COOK NUCLEAR PLANT - UNXT 2 AMENDMENT NO.

xuuzz IZHITING CONDXTXONS FOR OPERATION AND SURVEILLANCE KQXXQE 4.7.9 PIRE SUPPRESSION SYSTEHS e Suppiession Paean Syscee..... ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ 0 ~ ~ 0 ~ ~ ~ ~ ~ 3/4 7 27 Spray en 'inklec Systems.... ~ ~,0 ~ ~ ~ ~ ~ ~ ~ ~

'0 ~ ~ 0 ~ 0 0 '/4' 30 Kow Pressure C02 Sys ~ ~ ~ 1 ~ ~ 0 ~ ~ .)/4'.-34 HaLOn SySCem'0 ~

~ ~ 1 ~ ~ 0 i ~ 0 ~ '0' ~ ~ 0 ~ ~ ~ 0 0 7-'36 '3/4 P. se', SCLCions ~ ~ 0 0 0 ~ 0 0' p ~ 0 ~ 0 ~ ~ ~ 0 ~ 0 ~ 1 ~ ~ ~ ~ 3/4 7-37

.10 PIRE RATED ASSEHBLXES0 ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3 3/4.8.L. 'A.C. SOURCES Op el)CeLZlg 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ to 0 ~ ~ ~ ~ 0 0 3/4'+1 She@~ 'wreaao 0 0 ~ ~ ~ ~ 4 ~ ~ 1~ ~ ~ ~ 0 000 ~ ~ ~ 0 0 ~ ~ ~ ~ p 0 1 ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ a ~ 0 ~ ~ ~

eo 3/4' +%

3/4. 8;2 ONSITE PORNO .DXSTRIEOTIOS'.SKTIKS

'.Dis~ue1on -'Opera~g. '.

.C.

~ ~ ~ ~ ~ ~ ~ ~ 0 ~ 1 ~ ~

~

0. 3/4 '8 10

" A;C. Disaribueion - Shutdown.....'......;"........'.'..'.... 3j'4. 8-LX'.

D.C. Dis~bu&on - Opeca~g.......',...;....;..... 3/4 8-12 D.g. Disczibu&on - 'Shunner....; .. '...........;....., .. 3/4 8-16 .

D.C. DisMucion - Opceacing - Traia N Battery System. 3/4.8-17 3/4. 8. 3 ALTERNATIVE 'A.C. POQER SOURCE. 3/4 8-20 3/4.9.L BORON CONCZFECION0 ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ F 000. ~ ~ 0 ~ ~ 0 ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ 3l'4- 9-1 3/4.9.2 INSTRHTATION 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ 0 1 ~ ~ 3/4 9-2 3/4.9.3 D ECAY TIME 0 ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ 3/4 9-3 3/4. 9. 4 CONTAINMENT BUILDING PENETRATIONS 3/4 9-4 3/4. 9. 5 COMMUNXCATXONS ~ ~ ~ 3/4 9-5 COOK NUGAE~~ PLANT - UNIT 2 AMENDMENT NO. ~ 156

I, t

4, 7 (Cont:inued) 3/4. 7. 8 SEALED SOURCE CONTAMINATXON B 3/4 7-6 RE SUPPRESSION SYSTEMS 3/4,7. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 7-9

~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ B 3/4 8-1 G 0 3/4.9.1 BORON CONCENTRATION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ ~ o o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 9-1 3/4.9.2 INSTRUMEHTATXON o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ B 3/4 9-1 3/4.9.3 D ECAY TIME o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 'o ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 9-1 3/4.9.4 CONTAZHMEHT BUXLDING PENETRATIONS oho ~ B 3/4 9-1 3/4.9.5 COMMUNICATIONS B 3/4 9-1 3/4.9.6 MANIHJLATOR CRANE OPERABXLZTY .... ~... - ..

~ ~ ~ . ~ - - - - - - ~- B 3/4 9-2 3/4..9.7 Q4QG'. TRAVEL - SPBiT FUEL STORAGE BUILDING B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ........ B 3/4 9-2 3/4.9.9 CONTAZHMEHT PURGE AND EXHAUST ISOLATION SYS~ ....... B 3/4 9-3 .

3/4.9o10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o" B 3/4 9-3 3/4.9.12 STORAGE POOL VEHTILATXON SYSTEM . ~ . ~ ~ . ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ B 3/4 9-3 3/4:.9.13 SPENT FtJEL CASK MOVEMENT'. B 3/4 9-4 3/4.9.14 SPENT FUEL CASK DROP PROTECTION SYSTEM ............... B 3/CI 9-4 3/4.9.15 STORAGE POOL BORON CONCENTRATION B 3/4 9-4 3/4.10.1 3/4o10.2 SHUTDOWN MARGIN ......... ~.............

GROUP HEIGHT, XNSERTXON AHD POWER DXSTRXBUTION LIMITS.

B 3/CI B

10-1 3/4 10-1 COOK HUCLFAR PLANT - UNXT 2 XIII AMENDMEHT HO. 4O7-,  %$ 6, 175

1 t

I I[

J

STRUHEHTATZON FIRST DETECTION LHSTRUNEHThTZOH COHDITZOH FOR OPKUlTZON 3.3.3-8 a minimum, the fire dacaccion ins~encacion for each. fire detection t a shovn in Table 3.3-11 shall be OPERhBXE.

AyyXZCLBZZZZZ: ecever aqciynanc yrccaccad hy cha dire dace'ccdcn syscem(s) is zecphx;ed to be OPERh3LE.

,r kCZZCH:

Shan j

the number of OPH4ULLE fire dacectors is less 'than the. minimum number of requized OPERhBLE detectors given belov:

Shen any, buc noc more chan one-half the total or no tvo adjacen~

in any fire dataccion, sane, Function k dececcor(s) located oucside of concainmen+shovn in<

>> UMEHThTXOH 4.3.3.$ The fL' SURVEZIZANCK. RE OZRKKNTS e detection system for each fire detection ""r sone hee Qt TabLe 3.3-LL shaLL be chepnsmted OPERhSIZ as folly. 4.3.3.$ .L, Each of the detector the ah@re re fire detection systems which are accessibLe Cnring pLant+rati~ s~gdemonsmted OPERhBIZ at Least once per 6 months by performance a ClQgg5 FUHPiXOQL TEST. Fi e detectors vhich are not accessibLe baring t operation shaLL be demonstrated OPK4U3LZ by the performancit of a CRABKL PWCTXOHhL 'PST dcring. each COLD SHUTDOWNS exceeding 24 hoax)/tnLesa pMormed M the prana 6 months. ' .3-3.$ .2, The supervise etector aLarm circuits for the a detection systems sha].Z be demonsrrated OPEEhBLE at Least once perequired "e 6 nonths-Ma sagacrissd da~ceas a1axa a&~sa inclada aha dal.acme CiZCaita. K"I and ~bLe aL circnits from the remote fire protection con~L panel. the Con~ aLarm c om emergency fire con~L paneL, and andibLe fire and ~Le p ., ~7p)+>> / COOK NUC~ PLQiT - UHXT 2 3/4 3-51 (.) 'local Humber Bee Zlama (xfz)>> (x/y)>> )+ huxi Building a) Elevation 573 23/0 C b) Elevation 587 55/0 C c) Eleva~ 669 41/0 C d) Elevation 633 41/0 C l e) Elevacica~L650 34/0.C f) New Puel SAGE Area 4/0 C UZ East Naia S Valve Enclosure U2 HaLn Steam Line Area El. 612 (Around Chncainmenc) 13/~ U2 HEST Valve Area EL. 612 2/0 U2 .4iUT Svitchgear () 0/3 0/2 UZ 4K% SMtchgear (CD) 0/3 0/2 UZ Engr Safety System SM~gear & XBQL Rm.: 0/5 0/Z4 UZ , XFHR & Suitchgear Rm. Xnvez~r & S~. Rma. 0/5 UZ P essuri-er Beater'BQL UZ Diesel Puel Oil Transfer Rm. OP UZ Diesel Ceneracor Rm. 2AB 0 02 Diesel Ceneracor Rm. 2, 0/2 U2 Diesel Cenerator Ramp Coz . 4/0 Ul&2 Ar~P Vestibule 2/0 C UZ Conc=ol Room 42/0 UZ Svitchgear Cabl Vault 0/13 UZ Control Rm. CaSZe Vaulc 0/76~ U2 Aux,. Cable VMc 0/6 Ul&2 UZ ESV ~ Eas Perp enc Area HCC Rms. 4/0 9/0 C C Sy tarn protects area common to both Uni~ 1 and 2

• (x/y) is number of Pcnccion A (early +awing fire detection d notification only) instant" y is number of Puaction 3 (actuation of fi e suppression stems

~arnQxg and notification) inst~ants ancL'arly ~ ~ ci cuit concains boch smoke and flame detectors / evo ci cuits of five detectors each ~o circuits of 38 dececcors each '( .:/4 3-52 TABL"- 3 3-Ll (Con~d) U~c cLCo ~sec Toral Edger AJUS i'aioice ~e (~; (x/y)>> (x/y)>> r'/3 UZ Cable uanels a) Quad L CabLe Tuaael f b) Quad 2 Cable Tunnel 0/4 On c) QuacL 3H 0/3 O/3 d) Quad 3S ~ t/ 0/3 0/4 e) QuacL 3M 0/3 0/4. -) QuacL 4, 0/5 0/6 ~ i UZ Charcoal Zc Lce Vea~~oa U~cs a) b) 2-iVT-AES-L 2-iVT-AZS-2 0/L~ 0/L>>>>It>>>> c) 2-B'-ACR@ 0/L>>>>>>>>>> d) 2-iVT-CL< 0/L>>>>>>>>>> e) 2-iVT-QR r Q/L>>e>>>>>> =)'LZ -PT-AZX 0/L~tC UZ CoacaQugen~t>>>>>> a) QCP L ~L/0 b) 2 c) RC2 3 l ~$ /0 d) RCZ 4 L/d~ e) Cable "ays 64/Qwt>>~ I i ~g ,r' t C Syscem proceccs area common co boch Unim L ance 2

• (x/y) x 's number or cCac~oa 3, (early waxing ""'-e decec~oa aa noc'"cacioa oaly) Lascmmencs.

y ~ number o8 ."-unction 3 (acmaMoa or =~=e- suppression syscems and. ear'y'araiag ancL no~~~caMoa) iagc .uaeacs. Or'g'~LLy Las~led co aucomackcally cLel~e charcoal " ~cars. ", Someone, manual ac~ ons are no~ necessary. The ='re decec~on Las~acs Locaced requ'-ed co be OP~L= duroc vi~ ~ Conc'dmaeac are;noc che per ormaace or 'ice A Con~enc akage Race cesm.

berm'scors are LocacecL W~ aLL cabLe ays which concain combust~le.

cables, ~m boch boch upper and Lmrer conaaiameac ~oughouc ciuadrancs L-4" .I COOK VUC~iJL PLQPi - UNX 2 3/4 3-52a ~D~ ~ G 0 0 3.7.9.I. The- fixe suppression wacer syscem shall be considered be OP~L>> wich: Three fire suppression syscem pumps, + ach wi.ch a capacicy of 2500 gpm, with them discharge gned eo che fire suppression ,

b. o fire wacer tanks, 4'ach vi a num usable volume of 5,000 gallons (34.0 feec 1 indicacion)

Ci An 0 flow path cap e of caking succion from ei.cher one the fire vacer and eransf erring ehe wacer throu+ discribucion p ing (with. OPBUBLE seccionalizing valves) 'up co ehe yay hydzanc curb concrol valves, co ehe hose s on valye(s) and vacer suppression sys cern conczo valve{s) . The hose scacion valve(s) and ehe wacex'upp ssi,o'n syscem conczolling valve(s) thac are required eo b in the flow path axe given in Specificacions 3.7.9.5 and . 9.2; zespeccively. Ac all times'. hQXQK-Vi. 'ne p~'noper, e, zesroxe the &operable pump 'eo I lR+P. ~ scacus ~ ..'mich' ~ . ys or provide an aleexnace backup Qi.th,one'fixe wacer cant ino rabin, Mescoxe the -inop'e'rabI:e: eank. co'PERA'ILK 'seacus viehin 0 days or -esca&lish 'a supply. .backup'ace>>'yscem c . With the fixe suppxession wacer sy em ocher'vise inoperabLe:

l. fire '

Rescore ehe eo scaeus suppression within 24 ho,disczibucion wa or syseem . 2. Escablish a b .ckup fixe suppression cer syscem wi"Sin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. r ~ d'a The pzovisions of Specificacions 3.0.3 and ..'.4 are noc . applicable.' These pumps and tanks are shared between Un COOK NUCLEAR PLQFE'4 7-27 t 4.7.9.3.. The fire suppression water'ystem shall be demonscraced 0 LE: lease once per 7 days by verifying the water supply ntained in ch fixe water tanks'. Ac le c once per'1 days on a STAGGERED TEST TS by starting each p and operating ic for ac lease 15 min on recirculation flow. c Ac. lease onc per'3. days by verifying c each valve (manual, power operated, or automatic) in the w path chac is noc locked, sealed, ar oth ise secured in p sician, is in its coxrec" position.

d. At least above ground ance per internal 6

~ months by exfoxmance ion and of a system flush of fire hydrants.

e. by cycling each testable valve in the ne complete cycle af full travel.

Ac lease once per 18 nchs by erfoxming a syscem functional test which inc3.udes s ced aut cic actuation of- the system throughout its ope ting sequence, and: -3;; .Veri'fying c each automatic v ve in the flow path actuates to ics c ecc posicion,:- .. V chac each. pump develops a ow of ac lease 2500 gpm ac a head of ac least,.300. f'se of .wacer by observing: 'thx e cern po'ines '(@~num, raced ~cL ~ ak) on 'he pump '. ~ . ~ p oxmance curve ~ ~ '.3. Cycling each'alve in..De.'Q,ow path. 'that. 'na'c'ehcabl.e during pLane operant'%on,thxough"ac lease ons'o 'ees'ycl.e of full travel, and Verifying .that each . td.gh 'ryssure pump s in 'cs preplaxmed sequence to maintain the fixe suapxsssi water system pressur~'reater than or equal to 100 psig. Aa. least'nce,per 3 years by performing a series. of flow tests o

..chat every fire main segment (excluding indivt.dua3, syscem supplie

'as been verifi.ed co be clear af abs~cions by a gull. Q.ow test. COOK NUCLZAR PLASZ - UNIT 2 3/4 7-28 jl 0 4 4.7.9.I.. The fire pump diesel engines shall be demonscraced OPERAB c lease once per 31 days by verifying: L. The fueL scorage tanks contain ac lease 160 g lons of fueI., d Z. The esels scarc from ambient condici and operace for ac lease 0 minutes.

b. Ac Lease once p 92 days by verifying a sample of diesel fuel from the fueL sco ge tanks obtained in ordanoe with AS'-D4057-8X, is within the a cepcable Limits eoified in TabI.e I. oC ASTM-D975-8l when checks for viscosicy wacer and sedimenc.

Ci Ac lease once per 18 onths subj ecting the diesels co an inspeccion in accordance procedures prepared in conjunction wi.ch ics manufaccurer's re endacions= fox'his class of, scandby service. 4.7.9.1.3 The fire pump diesel s g b cary banks and ohargexs shall be demonscraced OPERABLE: .'. Ac lease once per .days by ve thac: I ~ .: ~../ The ele L7ce'.Level of each b ~ ~ exy is above the places, ' ~ 7...Th . oucpuc baccexy voltage of each b . is.'greacer than .24 . 4 volts 'b;. 'Ac ease onc'e per 92'.days b'y vezifIting thac the. ecMo gravi> <<ppriace for concinued:.sixvice of .each bacce'. Ac lease once per 18 months by verifying thai:

l. The batteries. oeLL places and baccexy packs. sho no visual indicacion of physicaL damage or abnormal deteriora on, and.

2. The battery-co-battery and terminal connections are .ean,

.tighc'ree'f oorjosion, and'oaced: with anti 'cod o ion material. ~~ ! COOK NU PLANT - UNXT 2 3/4 7-29 AHWDNWT HO. I 0 3.7.9.2 e spray and/or sprinkler systems located in the arM shown in Table 3.7- and 3.7-5B shaU. be OPERABLE: recpd.red to be PERABLE: / Vi.ch one op more of che vater spray tems as listed in Table 3.7-5A,.inop l able, wichin hour: l) verify chat the detection system for affected filtration c is OPKULBLE per Specification .3.3.8, ox 2) es lish a continuous. fixe vatch patrol.

b. Rich one or more o the sp er systems as listed in Table 3'.7-5B inopexable, within 1 our: verify chat at least one of the

~ deteccion systems, whe e p ovided (elec~c. per Specification .4.3.3.8 or pneumatic pe able 3.7-5B), fox'he affected area is OFERABLZ and escablish hourly. fixe. watch pacrol,. or 2) establish a .continuous fir'e vaM pa ol.>> Co The provisions of S ecificati 3.0.3 and 3.0:4 are noc appli,cable >> Fop .hf.'gh adiation areas, periodic monicoring (and hourly logging) @he closed circuit television coverage 1s an acceptable subset,cute for a ~ continuous fixe vatch. For vhexe closed circuit celevision coverage does noc'xist, an hourly fixe vacch pacrol will be ins ticuted. COOK NUCLEAR PIAHT.... DNXT'2 3/4 7-30 '" ": AtKHDMEHT NO. 44>, ~, 'I+ 4.7..2 ~~ of che abjure requL".ed vacer spray and/or spr~e= sys shall e demons~aced to be OP~L:-: gc Lease once pe L2 monchs by cycling each cescab e mime ""e Q,ow pach dmmxgh ac lease one complece cycle of zaLL a+el as os ded by Technical Specif'ca&on 4.7.9.l.l-e-

b. h,c ease once per 18 monchs:t per ocming a sys~ inc onaL case ~on ~Luaes cod aucomacio ac~~on of che sys, and:

a) ac r~g chac c& co che aucomacic cheir co~~cc posi& ml~ Ln De Q,mr pach on a case signaL ~ and+ b) g each ~me iu che pach chac is noc ~cable ~~ of jnLL Lane operacion throu l. ac Lease one oomplece cycle X.. By vtexaL ncion.of . uge. ancL preaocion syscam piping (chis is noc quired or syscems sup~ed by ai-) co very chai in 'cy

3. By vt.aml inspeeci of each open head deLuge nomle ca veri y chac chere o blockage.

C~ Ac.Lease once per 3 ears:by. er oxming an air ~ov arse ~ I head piping deluge'd of eaoh'n head de is unobs~ ge syscem and veri~ each ~ough'he oaen I g ~ i The p ~ious of Technical Sye~~caMon.4.0.8 are applicable. 'I "The =-e proceucion bracer Qatar surveillance'esc~g may be'suspended- ciX =".e Lec on of che =~ e procec"'oa'vicar"scoraje.caak.and 8 e.pump its 'a . cions 3l: .L'993) ..The suave'>>ance aas~g suspended. as. a "esulc o ch~ ndmenc 'will be hu.~cod ac ics normaL f equency +%chin" four'aonchs. oz Ne ~ . ne~.f' proceccion Macer scorage sacks and "' pumps'eing decla'red OP~L che excencion of uni' oucage requi=ed cescing ~hich +quid be comnlecad before che end af che'exc scheduled un'ic oucage. CQOV. hUC -31  %) 2-HV-AES Charcoal Hlters Eszuxal - ELec&c - He 2-HV-AES 2 a1 Filters HazuzaI. - ELec~c - eac 2-HV-ACRF-1 oal Filters Banzai - ELecai - Heac 2-HV-CPR-1 Chare FLlrers EazuuQ. - ELec c - Hear 2-HV-CXPX Charcoal F ers Hazuzal - chic - Heat 12-HV-AFX Charcoal FQ Hazuzal ELecMc - Heac r r~ +S ed syscem vt,ch Uzzic 1. COOK HUCLZBR PSST - QNZT 2 3/4 7-32 memo~ l a ~ aD Auxi building Preactian Sprint@,er Dry Pilo 7 fc.~/~ (Normally access le areas charging and Safe In) eccion Pump Rooms ~ s s co El. S73 and 60 Auxi1iary buil g Preaccion Spr&dcler Dry Pijo~ EL. 609 fc.+/ (Normally ~ accessible areas, Ctà Pump area, scairwa s co El. 633) Auxiliary building El. 633 fc.~/~ (No Preaccion ~er Dry Pilo~ accessible areas, excl Vestibule Areas and scaixways to El. 650) Auxiliary Turbine Driven Ve ipe Automatic 'Peechracer Pgep and: 'ump CorridoM/~ Turbine Building 59% fc.. ~ Vec Pipe AucomaC.c. ' EL. 'enerator End. (Extended to Diesel" ~ 'enerator Co~do~ 'Auxiliary Building'. Praaccion.dp~ Dry Pi1o~ .'Handling Area ( . 609} +/~ .Auxiliary Bui ng Drumming Preaccion SpriakLer Pilo~ (EL . 7) %/~ Reactor olanc. Pumps (4) ~ Preaccian Sprinkler Wyscam'rotects area common ca boch Units X. and 2. ~Dry Pilot Ac'cuacian .f.s considered ta be a hear. actuated pneumatic detection system. Located in areas which also have an aucamacic detection stem. COOK NUC~ PLAtlT - U~2 AHEHDHEQT NO. M4, 156 3.7.9.3 e low pressure systems located in the areas shown in able 3.7-6 shall e . required to be . h~H: With one or m re of the required low pressure systems isolated from automatic qperacion for personnel prote 2 on, verify that ac, least one cone o'ire detection for the ected area is per Specificacion .3.3.8 in order co pe c en~ for routine cours, maintenance, onscruccion, or s eillance testing. 'r With one or more of th required CO stems shown in Table 3.7 , within 1 ho: I.) ve at least one cone of fire detection for the,affecce area is PERABLE per Specification 4.3.3.8, and establish a f wa patrol co inspect the affected fire area once per hour, or kcablish a continuous fi e watch co the affected area.. 'atrol The provisions of Specific ions 0.3 and 3.0.4 are noc.. applicable.' '4.7 9.3 ~ of the above Each florio r ed low 'pressure CO sysc'ems. shill be ~ demonstrated: OPERABLE:, ~ '. 'Ac be leas'c once per 7 days by.verifying the CO' s rage. greater tha or equal co 50% and pressure .2 to b greater chan or ~'level co equal to 285 psig, and b.' Ac leisc ce per 31 days.by verifying that e~ val& in . che path is in the correct position. b.. At 1 c once per 18 months by.verifying: 1 The systems valves, associated vencilaaion .and ans,

and self-closing fire doors operace automatically upon ceipc ~

of a simulated actuation signQ, and 2; Syscem actuation mechods ~ (automatic from detection system, manual pushbucton stacion, manual pneumatic release) are cesced cb ver~ proper actuation of the system.

3. Flow from each nozzle during performance of an air Q.ow or CO2 "Puff Tesc".

Diesel Gene cor 2kB Room Cross- aed Heat Diesel Genera 2CD Room Cr s-Zoned Heat Diesel Generator 1. Oil Pump Room 41UT SMcchgear Rooms Hxxnual Coacrol Rod Drive, Tr . Swicchgear Rooms Manual Engineered Safety Svicchge Room Maxxual SWcchgear Room Cable Vault Cross-Zoned Zonizacion and Znfrared Atad.lazy Cab1.e Vault Ionization ~ Coacrol Room Cable Vault (Bac )+ Kinual P Penlai ation Cable Tunnel anc 1 Haau:Ll ~ Penecrac'n MaxxuaL. Penec a@ion Cabby. T e1. Quadranc 3N' Manual Feei ation Cable'anel Quadrant'3M Haxxual .'Cab e Tunnel hydrant'S ' 1 Penec-acion le Tunnel hydrant 4. ~control Rbom Cable Vau1.c System is only required to be W th Cab1.e Vault Halon System is . COOK NUC~c pr 3/4 7-35 HEHT %0 64 ~ 15o 3.7.9. The Halon system located in the Co~wl Room Cable V c shall be OPERABL whenever equipmenc in the Hai.on pzocecce area is required co be . h~H-

a. arith the Halon System isolated m automatic operation for perso el proceccion, verify c ac least one zone of fire

. dececci for the affected is OPERABL" in order co pe~ en~ in the cable vault.

b. Rich the ab required on syscem inoperable, vichin 1 .:.

hour. 1) ve chat a lease one zone of the fire detection, syscem and the b c CO fire suppression system for che" affected area are 4.7.9.3 zespecciv, 4 per Specifications 4.3.3.S and ~ 'acrol. or 2) escablish a continuous fire vacch c.. The provisio . of Spec i.caciona.3.0.3 and 3.0.4 are'noc 'applicable,' 1 4.7;9.4 The above re 'ed Halon'yscem shall be demonstrated..OPGM3L:": '" a.." Ac ease once per 6 monchs by g, each HaXoa storage'. '.. 'co be. greacez'th'an 'or. equaI;". 95% of full charge hei,'ghc" appzopriace'iquid. level, 'and co e greasier than er'equal. 90% of full charge.pressure correl ed for ambient ~ temperature. Ac least once per 18 months by'.

1. Verifying the system (including assoc ced vencilacion dampers ancf .fans, and doors) is- tested r'proper operation by a simulated'actuation si:gnal

/ '2.. System.ac~cion'methods ('automatic f om dec cion system, manual pushbuccon scacion, and manual linder actor) are co be tested. to verify prope .ac 'on of ~ the system.

3. Performance of an air flmr test or CO puff test thro headers and nozzles to assure chac there is no blockage.

COOK NUCLEAR PLANT - QÃZT 2 "T 4 NO.4, ~ 3;7.9. The fire hose stations showa in Table 3.7-7 shall be ERABLE: whenever aquipmeac,in the areas procecced b the fire hose stations required co be . Vi one or moze of the fixe hose scaci shown in Table 3.7-7 ino rable: 1) For those areas where the fire'ose sca n is the prissy means of fire pression (areas where no fixed stems are provided or'r where the Qxed syscems are inoper e), within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, route additional equivalenc capacicy fire hos co the affecced area(s) from an hose station(s) per Spec cation 4.7.9.5, or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, verify that the fixed fire pression sysc s) chac also protects che affected area(s) se ed by the fiz ose scation(s) is . The provisions applicable. o f Spe icacioas 3.0. 3 aad 3.0. 4'xe not S 4.7.9;5 ~, of .demonstrated '::: che. fire os scacions shown in Tabl'e 3.7-.7 shaLl be . a...Ac lease once stations co er.3X days sure all ze i visuaX, inspecti'on of the fire hose ed equipmeac is aC the,station. ~ J

b. " Ac.lease" e 'per 18 months by.

1: .'-'he. hose ~ for ~ 'inspection aad.re-racking, C ~ ~ ~ and ~ '- .'* ' ." 2.,' Kep'lacement.of .aXl degraded g kecs in'oupUngs". ~ 'l ~

c. Ac east.once per 3 yeazs by:

Partially opening each .hose' ion valve co . veri y OPKDLBZLTTY and no flow blockage.+ 'r II J '2; . Conducting a hose cesc. ac a r'essure..of MO pang ' . at lease 50 psi greater chan -the,suacinmja 'pressure 'I available ac that hose scacion, whichever greater ~ fire pzoceccion water'low surveillance eesciag may be susp. ded until the c 'ecion of the fire 'protection water scozage tank and Q e pump calm~cions

31. 1993) . The suzveillaace costing suspended as a re 'of this amendmenc will be ini.ciaced ac 'ics riozmal frequency within <ouz mon of c'te

'new fire protection water storage tanks and fire pumps being declared OP L:-, with che excepcion of uni.c outage required case'ng which would be compl ed before che ead of W~e nexc scheduled unit oucage. lW MS-h Aux'ax@ Buil Access co Diesel Gene r Rooms ose Sraeton No. 7 Access co Swi,noh@ear Rooms Hose Sue&on No. 45 or No. 212 Access uo Control Room Hose Scaeion No. 65 or No. 81 Access co Pressurizer H r Transformer 'ose Sea@ion No. 12 Room Access uo oms, HCC Room, and Hose cion No. 20 Basemenc Ar Access co liaxy Feed Pump Rooms 'Hose Scan%on . 9 shared &eh Unit 1 Mdn the Con@rolled Area i ~ COOK NUCLEAR PLANT - UNIT 2 l k %3 3.7.10 Pire raced assemblies shall be as follows: fixe raced assemblies (waLls, floor/ceilings, d cable cxay conduic enclosures), sepaxacing safe shu fixe areas or sep acing porcions of redundanc syscems impo c co safe shucdown a fixe area shall be .

b. All pen acion sealing devices (fire doo assemblies, fixe dampers, penecxacion seaLs for cabl around. conduic, cable cxay, pip and vencilacion duce wor in the above fixe raced assemblies 1 be OPERABLE.

Ac al1 es. hQXXQE:

a. Sich any of che above ixe aced assemblies and/or sealing 'dev'ices inoperable, wichin L ho ..1) verify chac che fixe dececcors and/or fixe suppressio scam on ac lease one side of che

&operable assembLy ' LZ and oscablish an hourL+ fixe wacc ~ .. of che penecracion. or'3) se e.che', seali'ng Mvice+'n ~ che.closed posi n, and escab h an hourly fix'e wacch pacxoL, or (4) for fire ers and normall. locked Me doors, secure che ' s 'evice in che c osed'posiMon;~ I b; The'xovisi of Specifi'cacion 3.0.3 and 3.P.4 are noc..apylicabl'e. ~ ~ F A C 4.7.10.1 Ac asc 'once'per' monchs che above re ed fire raced assemblies an penecracion seaLing devices shall be ve ied by:

a. P rfoaning a visual inspeccion of all accessible sur aces, of each ixe raced assembLy, for open penecracions.

b. PeMorming a vi~1 inspeccion of each fixe damper '.'cs associaced hardware'.

c'. Performing a Funccional Tesc, requiring closure cescing '0% of... che .fixe .~ Excepc fire doors on Turbine Driven Auxiliary Feedwacer Pu'mp and HalL ay enclosures which muse remain open due to considexacions. ~is cescing is in addition co che cescing required by Specificacions

4. 7. 9.3. c. 1 and 4 7. 9.4.b. l.

~pcion (4) should be used for fire only afcer ehe appxopriace C and radiologicaL reviews have been performed. Rl!M)NEHRU NO. I~ Con'

d. 'Performing a visual inspection of at least 10 percent of each e o enetration seal (cable, around conduit, cable tray, pi g, and ven ation duct work penetration seals; and cable tray d conduit enclo s required for Appendix R compliance) . Xf arent changes in+appearance or abnormal degradations are und that could indicate a p t vide trend, a visual inspection an additional 10 percc of type of penetration seal s be made. This.

inspection process 1 continue until a 1 ercent sample erich no appazono ohangaa fn appaazanoa oo abno dagoadanLon ia found. 4.7.10.2 Each of the required fire ors s be verified by: a. b. Inspecting the hold-open, latches at least once per Verif~g the position 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. o 6 I releas'nd months. closing each cI.osed ff:ge door mechanism and at least once per

c. Verifying that do s vith hold-open and releas mechanisms are free of obstructio t least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

~ da VerifIdag a'positiozj of 'each locked closed fire doo at,leis'. .once p days. 4.7.M.3 mcfmg'repairs or'aintenance on an ebon required fire" ed .. 'be v'edr assembl . s'ealing 'devic~, 'the fire "r'ated. assembly or sealing device s to be. .'before ~ting the applicablge action statement. hD~~~i- CONTROLS

b. kc lease oue Licensed Operacor shaLL be fa che con~L room vhen ueL is ~< che eaccot. Zn addicion, vhile che cni 9 ~x %de L,

~

2. 3, or 4, ac Lease one Licensed Senior Operacor shaLL be in che coal Co km individuaL qaaL'~ied Ln radiacion proceo-ion procedurea shaLL be on sice vhen ueL Q in the reacaa.

d. hLL CORE hLZK~AHS shaLL be d'-curly supe+aed by a Licensed Senior Operacor ~ized or quaLMied m efue~g end CARE hI~hLTZANS (SQ-Ch) vho has co ocher concur=enc esponsQilicies during chis onsic of or ce 'w c

che ndxaDram 'h opera~ brigade of ac lease socnel repel=ed for och 5 ~d sary for shall be naincained noc includ 3 memb rs safe shucdovn of cheun'.c SM~4 cxc&g The amounc of ove ~me vorkad by plane scaff members per'mating safecy-reLaced uno ons muse be ~cad in ao" danoa vi~ HRC PoLicy Scacemenc on vor~ hcnaa,(CenMw Lac~ 82-LX). ~ The ~~ Supervisor, chal'old ~ hssiscsnc Supervtso>>, and Qai= ~ense. , Supatvtsor a Senior Operacoc Mi Qperacor License ac Cook Nuclear ?Lane or a st Operacions Supe wcendenc muse hold or have held a Senior Md LeveL Opewcions Pwchc~~ Super>or shaLL hold a cu enc Sex~r Ope~cor Mcense. reaoae 4nd one ~cyp~(fog ah serac~ sos ~ p~r>>d' ~*~ 5 % 0 g,'.4 g4r'v'QaP f~+~~<<~JI g pr-~+ proce&r d" s p~ ~~ Wg Prov 4 <<~+egraw ac~ ~ o> o l I /g Mc ~~~ ~ &I I/ Qg r'~~ ~i I c?g / composicion o~g" ace~br gacte-ma~ Less ~~Ne min'~.<<~emencs cnexpeccad absence gav5fad m4ediaca ac~ post <<4 CQQK HUC~ PLhHT - UHX~ 2 6-2 B 0 6.8.1 Vritten procedures shall be established, implemented and maintained covering the activities referenced below:'. The applicable procedures recoamnded in Appends h of Regulatory Cuide 1.33, Rev. 2, FcLbruary 1978.

h. Deleted.

c. Deleted.

d. PROCESS CONTROL HUKRhH implementation.

e. OFFSITE DOSE CALCQIhTION MhRlhL implementation.

f. Quality Assurance Program for efQuent and emrironmenta1, monitoring using the guidance in Regulatory Guide 1.21", Rev. 1, June 1974, and Regulatory Cuide 4.1, Rev. 1, April 1975.

4.8.2 Each procedure and administrative policy of Specification 6.8.1, above, and changes thereto, including temporary'changes, shall be reviewed prior to implementation as set forth in Specification 6.5 above. a 6.8.3 A plant program for post-accident sanpling shall be established, implemented, and maintained vhich will ensure the capability to obtain samples, containment atmosphere noble gas samples, andand'nalyze unit vent gaseous effluent samples for and particulates under accident conditions. The program vill include the following:

a. Training of personnel,

b. Procedures for sampling and analysis,

c. Provisions for maintenance of saarpling and analysis equipment.

COOK NUCLM - UNIT 2 6-13 The OPKMSXLXTY of the post-accident instrumentation ensures thac sufficient information is available on selected plane parameters to monitor and assess these variables Curing and following an accidanc. 4337 e> 4 8 0 OPERABXLX the fire detection instrumentation ensures that fi .. capabi~ is ~avao.able for the prompc detaccion of . This adequate'arning capability is require order to detecc and locate fir n their early prompc dececcion o&fires will reduce the potbncial for damage co 'tages. safety-reI.aced equipmenc and is ~cegraL element in the overall facility fire protection program. Xn the event, tham a porcion o e fire deteccion hutromencation is , the establishment of frequenc fire patrols the affected areas is raqhhized to ovida dececcion capabiLity untiL the parable. instrumentation restored to OPERABXLXTY. Use of containment temperature is>> ~ monitoring inopazaM.e. alI.owed once per hour if concainmenc fire detection This ins~ancation includes provisions for monicoring the concencracions of pocanciaLLy explosive gas mixcures in the Waste Gas Holdup System. The OP~XLZTY and usa of this ins~entacion is consistent with the requirements of General Design Criceria specified in Seccion U..3 of the FinaI Safecy AnaLysis Report for tha Donald C. Cook Nuclear PLant. This specificacion is provided to ensure that the turbine protection instrumentation and the turbine speed control vaIves are OP-qABLZ and wiI.l procecc the turbine fram excessive . Protection f om "u bine excessive ovarspeed is required since excessive oversoeed of tha turbine could generate potentially damaging missiles which could i-pact and damage safety relaced components, equipmenc or structures. COOK NUC~~ PLANT - UNXT 2 B 3/4 3-3 AP~Y K NO. 44, 44$ , 44%, L75 included co ensure that the periodically uadergo a perfoxmance evaluatioa in view of their age and operating condicibns. These records wiLL provide statistical bases for future considexatioa of service life. The requirements for the maintenance of records and the sexvice Life review are noc intended co affect plant operation. The number of saubbexs to be functionally tested duxiag each suxveillaxme is based on calculations perfoxmed co allo~ exceasion of the suxveillance incexval from 18 months co 24 months, and therefore, the number of saubbers &mccionally cesced deviaces from the number xequired by the @espouse Standard Technical Specifications (, Revision 4) . A lisc of individual with detailed iafoxmacioa of saubber Location and size and of system affected shall be available at the plane ia accordance with Section 50.71(c) of . The accessibilicy of each shall be detexmiaed and approved by the Plaac Nuclear Safety Review Committee. The decexmizmcion shall be based upon the existing xadi.ation levels and che expected time to perform a visual inspection ia each Location as well as other faccors associaced with accessibility during plant operations (e.g., temperature, atmosphere, locacioa, ecc.), aad the xeconnnendacioas of Regulacoxy Guides 8.8 and 8.10. The addicion ox'eletioa of'ny shaLL be made ia accordance with Seccion 50.59 of 10 Parr. 50. 4 The Limitations on removable coacamixuLcioa for sources r'equixiag leak ~ ~ 1 testing, incL~4g alpha esIitcers, is baied "oa . 70 39(c) Limiis fox'. , I . 'This LintLtation easure thqc'leakage from byproduct, source, and. special nuclear.material sources wi11 not excee'd allowable iacake values. ' 'V of .cher ~~e suppression s'yscems eaiuxes chat adequace e PERABlLZVC in aay po oa capability. W available. co'onfine and ~gush of the facility'where safety relaced equipmea~cWlocaced; fir, occurring'uppxe The fire suppre on system consists of. the wacer system, iay and/or spriaklexs, che fire ,:sys suppress'ioa and fixe hose. stations. The col ective capability of is adequate to miaizgc5 potential damage to saf ecy-related 'equipment a ma)or eleme in the facility'fixe protection program. In the event that one ac~cion must.be isolated for ox'ore ~ rsonal'proce pres 'I n systems reglizizlg automatic oa to pexmf.c entry for. routine couxs, maincenaace, 'ruccion, or ReLiance oa the fixe dececcioa system, ia con)un ~ maznuLLLy dischax'ge the 'n a manual with suppression system, wiLL p de ~ adequa fire pxoteccioa for periods when personnel axe required to work the areas. COOK NUC~ P~ - UNIT 2 B 3/4 7-6 AHENDMEHT NO. 1Q, ~56 M, M4, ~, M4, N, I'fS S S S 4.7.9 ~ Co ued Zn the event that portions o f the fire suppression systems are , alcernace backup fire fighting equipment Ls required to be made pvailable in the effected areas until the equipment is restored ervice When the fina-fighting equipmsnC is intended for use a backup means of fire euppressioa a longer period of time is a&owed to provide an alternate means of Me fighting than if the equipment is Che primary means of fire suppression. Backup fire pcyteccion equipmenc will normally take the form o&.permanently mounted fire eictinguishers and/or fi "e hose scacions in or near the. area, or fire hoses routed to the affected area. However, it is noc our intent W rely on bacJcnprsyscems or other compensatory the portions of the within a reasonable period. ~ measures for an-extended period>of time and action will be taken to rescor'e su ssion system to OPERMKZ status The surveillance requirements provi as ance that the a~zm OPERMZZZTY requirements of Che fire suppression systems are meC surveillances specified in 4. 7+ 1.1 the f ~ scill capable of performing itm intended funccian. consequently, Wake per orming suppression water system is ic's not necessary co enter the A~QN sTKTEMENT specMied in 3-7.9.], while the SURVEZLLlLNCES specified in 4.7.'9.'l.l are being performed, unless the tested equipmena fails the SURVEXLLANCE. ~ ~ allowance is made for I Xn addition, ensuring a sufficienMvolume of Salon and in the~Salon tanks by verifying a.Cher Che weight, level, or pressure of the tanks. and ~ storage The fire suppression water system has three fire pumps ccaamon co boCh units which dischydge into underground ring . There is cite. moto~iven horironcai~encrifugal fire pump rated aC 2500 gpm that takes suction C~ the fire wa storage tanks; and two diesel~ngin~iven horirontal cent=ifugal fire s rated at 2SOO gpm that take suction from the fire wa~ storage Having a combination of diesel~iven and elec" ic~to~ivin pumps the system design is consistent with NRC Branch Technical Position ~APSCS S l.

• COOK NUC-KR PLANT UNIT?---,,~3/4 7 ~AHENDHENT NO.

~ eo Revised by NRC letter david'December 14, l.994 BASES 3 .7.9 Conc nued The purpose of the charcoal fQ,cex fixe suppression T/S is ta account for dececcion and suppression of fixes in the charcoal fQ.ters. EamuLL opepreion of these s cems is allowed because cwo-point heat decaction Wth control room and local ciaeion of trouble conditions is provided for the charcoaL filters. The IZZTT of che fixe suppression system the chaxcoal. fileers only required vhen chere is charcoal. protection@ in the fQ.cars. opening of che system isolation valve and reaching che seepoint for the automat opening of the system deluge ~ hacuaeion of spray mxer onto the charcoal fQ.ters requires~both the manuaL temperature aLaxm valve. Because of the inaccessibili~of the Lower canca&menc to personnel during operation due eo hLhKL xadia exposure concerns, che use af one or mare in the Lover canaaimaenc, eo cor fcx fixe and smoke, is an acceptable substitute to a cone giga mech, ig the fire suppression system becomes . LLl hourly fixe mech patrols a margin of fifteen aLinuees. axe pexgoxme&ae intervals of s~ adnuees Mch 4 continuous fire vatch requires that a trained viduaL be in the spec'&ied area ae aLL times and thae eaEch fire sane vithin the~ecified area be patrolled ae Lease once exrexy fifteen minutes vf,th a margin ag five minutes. r 4 concrol valve is defined as a valve that vhen cl,osed doe noe leave an alternate open fl paeh eo a system. 4 seceionaL&ing valv~e valve chat vhen osed does noe prevent an alternate open glar path co a defined as a syscem and hen does not make che fire suppression mter syscam . Under c situations, che closure of a sectionalXcing vaLve fo d by the closure;of a second valve vtLL noe l,eave an open glor path to one%of the specifiedisyseems. Xn this inseance, Action Seacemene c of Specificaehna 3-7. 9.gL* applicable. KunuLL actuation of CO> fire suppression syscems provides adequace for the protected areas based on Are detection in che fixe'Wceccion ,ci ea, Lov combuscible Loadings ~and prompt fixe.,3rLga4~erp ~ - ' - ' .- COOK NUC~~ PLAHT - UNXT 2 %A ~/AS 3 4 7.9 Cone ued Many of 'the hccion Statements take credit for OPERhBIZ fire detection in 1 u of a fixe watch vhea a fire protection system is . OPERhBIZ e detection provides sufficient early vaxniag capability of a fixe to e appropxiate Contxol Room. Darius Smvai11anas fessing of a Lov Pressare Co 2 system the aysaaa , the requirement for a continuous fire vatch y be suspended during portions of the test vhich result or may resul in a discharge iato We CO protected area. Similarly, if a accuation ccuxs erable, vhich results in We che requirement for aced to have the Lov Pressure'.CO%2 Sysce2 made a coacimunxs fixe vatch may be suspended. In iWer case, the area affected shall be rescored to habitability as soon practicable, after vhich che continuous fix'e vacch is to be re-estab hed if the system is still . 347. 0 The OPERhBILXTX of the fire ers and barrier penetratioas easures that fixe damage vie. be limit . These desiga featuxeshainhnice the possiMlicy. o8 a single fixe invol~ more than one fixe area prhu: to detectioa aad extinguishment. The e barriers and fixe baxxi.ex penecxacioa sealing devices are perio y inspected to very~ theM OPERhBIEKXT; The functional tes of the fixe . M provided to ensure ~c We remain functi . The veatilacioa seals are seals axoaad vemC9,atioa dace work penecra g fixe baxrf,exs. Zc is aoc our intenc to rely aa bachap syscems or other compensacoxy measures for an extended period of tima aad hCTIOM be taken to restore the iaoperable portions of the fixe raced assem to OPERhBIZ status vithin a reasonable period. F the purpose of determining OPERhBXLXTY, an OPERABIZ fixe raced ssembly/sealing deMce is oae that is capable of pexfozmiag its intended saf ecy function. COOK HUCIZAR PLANT - UNIT 2 ATTAABfENT 3 TO AEP:NRC:0692CX REVISED LICENSES AND THE T/S PAGES, AND APPLICABLE JULY 1994 PAGES Docket No. 315 Page 4 of 6 Amendment 2.C(4) Power Company shall implement and maintain, in Nos. 31, 194 effect, all provisions of the approved as described in the Updated Safety Analysis Report for the facility and as approved in the dated June 4, 1979, subject to the following provision: The licensee may make changes to the approved without prior approval of the Commission only those changes would not adversely affect the ability to if achieve and maintain in the event of a fire. (5) S ent Fuel Pool Stora e Amendment The licensee is authorized to store D. C. Cook, Unit 1 and Unit 2 No. 118,136,169 fuel assemblies, new or irradiated up to a total of 3613 fuel assemblies in the shared spent fuel pool at the Donald C. Cook Nuclear Plant subject to the following conditions: Fuel stored in the spent fuel pool shall not have a nominal enrichment greater than 4.95% Uranium-235. (6) Deleted by Amendment 80. Amendment (7) The px'ovisions of Specification 3/4.9.7 are not applicable for No. 169 loads being moved over the pool for the duxation of the spent fuel pool reracking project. Control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of "Controls of Heavy Loads at Nuclear Power Plants." Administrative controls shall be in place to prevent any load not rigged in compliance with the criteria of from passing over the spent fuel pool with the crane interlocks, required by T/S 3/4.9.7, disengaged.

• 2.D Ph sical Protection The licensee shall fully implement and maintain in ef feet all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions o f the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Xnformation protected under 10 CFR 73.21, are entitled: "Donald Amendment C. Cook Nuclear Plant Security Plan," with revisions submitted No. 122 through July 21, 1988; "Donald C. Cook Nuclear Plant Training and Qualification Plan," with revisions submitted through December 18, 1986; and "Donald C. Cook Nuclear Plant Safeguards Contingency Plan," with revisions submitted through June 10, 1988. Changes made in accordance with 10 CFR 73. 55 shall be implemented in accordance with the schedule set foxth therein.

INDEX LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIALFLUX DIFFERENCE .. 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO .. 3/4 2-11 3/4.2.5 PARAMETERS 3/4 2-13 3/4.2.6 AXIALPOWER LEVEL ................ 3/4 2-15 3/4.3 INSTRUMENTATION 3/4.3.1 SYSTEM INSTRUMENTATION 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION . 3/4 3-15 3/4.3.3'ONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-35 Movable Incore Detectors 3/4 3-39 Seismic Instrumentation . 3/4 3M Meteorological Instrumentation 3/4 3Q3 Instrumentation 3/4 346 Post-Accident Instrumentation 3/4 3-54 Explosive Gas Monitoring Instrumentation 3/4 3-57 3/4.4 3/4.4.1 LOOPS AND COOLANT CIRCULATION Startup and Power Operation 3/4 4-1 COOK NUCLEAR PLANT-UNIT 1 V AMENDMENT83, 440, 489 0 INDEX LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.8 ELECTRICAL POWER SYSTFMS 3/4.8.1 A.C. SOURCES Operating 3/4 8-1 Shutdown 3/4 8-9 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A,C. Distribution - Operating 3/4 8-10 A.C. Distribution - Shutdown 3/4 8-11 D.C. Distribution - Operating 3/4 8-12 D.C. Distribution - Shutdown 3/4 8-16 D.C. Distribution - Operating - Train N Battery System 3/4 8-17 3/4 8.3 ALTERNATIVEA.C. POWER SOURCES . 3/4 8-20 3/4.8.9 REFUELING OPERATI NS 3/4.9.1 CONCENTRATION 3/4 9-1 3/4.9.2 INSTRUMENTATION 3/4 9-2 3/4.9.3 DECAY TIME 3/4 9-3 3/4.9.4 CONTAINMENTBUILDING S 3/4 9A, 3/4 9.5 COMMUNICATIONS 3/4 9-5 COOK NUCLEAR PLANT-UNIT 1 AMENDMENTQ3, 400, 4', ~ INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS Continued 3/4.7.8 HYDRAULICSNUBBERS B 3/4 7-5a 3/4.8 ELECTRICAL POWER SYSTEMS B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 CONCENTRATION .. B 3/4 9-1 3/4.9.2 INSTRUMENTATION . B 3/4 9-1 3/4.9.3 DECAY TIME B 3/4 9-1 3/4.9A CONTAINMENT BUILDING S B 3/4 9-1 3/4.9.5 COMMUNICATIONS B 3/4 9-1 3/4.9.6 MANIPULATORCRANE B 3/4 9-2 3/4.9.7. CRANE TRAVEL - SPENT FUEL STORAGE BUILDING B 3/4 9-2 3/4.9.8 AND COOLANT CIRCULATION ............. B 3/4 9-2 3/4.9.9 CONTAINMENTPURGE AND EXHAUST ISOLATION SYSTEM ............ B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACI' VESSEL AND STORAGE POOL 3/4 9-3 3/4.9.12 STORAGE POOL VENTILATIONSYSTEM B 3/4 9-3 3/4.9.13 SPENT FUEL CASK MOVEMENT B 3/4 9Q 3/4.9.14 SPENT FUEL CASK DROP PROTECTION SYSTEM ... B 3/4 9X 3/4.9.15 STORAGE POOL CONCENTRATION B 3/4 9P 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS .. B 3/4 10-1 COOK NUCLEAR PLANT-UNIT 1 AMENDMENT&, 420, ~, 480 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3 INSTRUMENTATION Page Intentionally Deleted COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-51 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION Page Intentionally Deleted COOK NUCLEAR PLANT-UNIT I Page 3/4 3-52 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUHKMENTS 3/4.3 INPIRUMENTATION TABLE 3.3-10 Table IntentionaHy Deleted COOK NUCLEAR PLANT-UNIT I Page 3/4 3-53 AMENDMENT%)-QO, 448 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIIKMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-10 Continued Table Intentionally Deleted COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-53a AMENDMENT430, ~, 486 6.0 ADMINISTRATIVECONTROLS 6.2.2 Continued At least one licensed Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in Mode 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

d. All CORE ALTERATIONS shall be directly supervised by a licensed Senior Operator trained or qualified in refueling and CORE ALTERATIONS (SO-CA) who has no other concurrent responsibilities during this operation.

e. The amount of overtime worked by plant staff members performing safety-related functions must be limited in accordance with NRC Policy Statement on working hours (Generic Letter 82-12).

The Shift Supervisor, Assistant Shift Supervisor, and Unit Supervisor shall hold a Senior Operator License. The Operations Superintendent must hold or have held a Senior Operator License at Cook Nuclear Plant or a similar reactor and one mid-level Operations Production Supervisor shall hold a current Senior Operator License. The unexected absence, for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, of the on-site individual qualified in radiation protection procedures is permitted provided immediate action is taken to fill the required position. COOK NUCLEAR PLANT-UNIT 1 AMENDMENTW, ~, 484 1 6.0 ADMINISTRATIVECONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Rev. 2, February 1978.

b. Deleted.

.c. Deleted.

d. PROCESS CONTROL PROGRAM implementation.

e. OFFSITE DOSE CALCULATIONMANUALimplementation.

f. Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974, and.Regulatory Guide 4.1, Rev. 1, April 1975.

g. Fire Protection Program implementation.*

6.8.2 Each procedure and administrative policy of Specification 6.8.1 above, and changes thereto, including temporary changes, shall be reviewed prior to implementation as set forth in Specification 6.5 above. V 6.8.3 A plant program for post-accident sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze samples, containment atmosphere noble gas samples, and unit vent'gaseous effluent samples for and particulates under accident conditions. The program will include the following:

a. Training of personnel,

b. Procedures for sampling and analysis, C. Provisions for maintenance of sampling and analysis equipment.

COOK NUCLEAR PLANT-UNIT 1 Page 6-13 AMENDMENTV4, 4$ 4, 489, 4$ C 3/4 BASES 3/4.3 INSTRUMENTATION 3/4.3.3.5 INSTRUMENTATION The OPERABILITYof the instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room. This capability is required in the event is lost and is consistent with of . 3/4.3.3.5.1 APPENDIX R INSTRUMENTATION The OPERABILITYof the Appendix R instrumentation ensures that sufficient instrumentation is available to permit shutdown of the facility to COLD SHUTDOWN conditions at the local shutdown indication (LSI) panel. In the event of a fire, normal power to the LSI panels may be lost. As a result, capability to repair the LSI panels from Unit 2 has been provided. If the alternate power supply is not available, fire watches will be established in those fire areas where loss of normal power to the LSI panels could occur in the event of fire. This will consist of either establishing continuous fire watches or verifying of fire detectors per Specification 4.3.3.7'nd establishing hourly fire watches. The details of how these fire watches are to be implemented are included in a plant procedure. 5 ~ 3/4.3.3.8 POST-ACCIDENT INSTRUMENTATION The OPERABILITYof the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident. COOK NUCLEAR PLANT-UNIT 1 Page B 3/4 34 AMENDMENT74, 488, 486 3/4 BASES 3/4.7 PLANT SYSTEMS 3/4.7.8 HYDRA LICSNUBBERS Conti ued The visual inspection frequency is based upon maintaiaing a constaat level of protection to systems. The method for determining the next interval for the visual inspection of is provided based upon the number of unacceptable found during the previous inspection, the category size for each type, and the previous inspection interval per NRC Generic Letter 9049. A is considered unacceptable if it fails to satisfy the acceptance criteria of the visual inspection. Aay inspection whose results required a shorter inspection interval will override the previous schedule. When the cause of the rejection of a is clearly established and remedied for that and for any other that may be generically susceptible, aad verified by inservice functional testing, that may be exempted from being counted as . Generically susceptible are those which are of a specific make or model and have the same design features directly related to rejection of the by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration, When a is found , an engineering evaluation is performed, in addition to the determination of the mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the . The engineering evaluation shall determine whether or not the mode of failure has imparted a significant effect or degradation on the supported component or system.. To provide assurance of functional reliability, a representative sample of the iastalled saubbers will be functionally tested during plant shutdowns at 24 moath intervals. Observed failures of these sample shall require functional testing of additional units. The service life of a is evaluated via manufacturer's input and information thtcugh consideration of the service conditions and associated installation and maintenance records (newly installed , seal replaced, spring replaced, in , in high temperature area, etc...). The requirement to monitor the service life is included to ensure that the periodically undergo a performance evaluation in view of their age and operating conditions. These records willprovide statistical bases for future coasideration of service life. The requirements for the maintenance of records and the service life review are not iatended to affect plant operation. The number of to be functionally tested duriag each surveillance is based on calculations performed to allow extension of the surveillance interval from 18 months to 24 months, aad therefore, the number of functionally tested deviates from the number required by the Standard Technical Specifications (, Revision 4). A list of individual with detailed information of location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of . The accessibility of each shall be determined and approved by the Plant Nuclear Safety Review Committee. The determination shall be based upoa the existing radiation levels aad the expected time to perform a visual inspection in each location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and recommendatioas of Regulatory Guides 8.8 and 8.10. The addition or deletion of any shall be made in accordance with Sectioa 50.59 of . COOK NUCLEAR PLANT-UNIT 1 Page B 3/4 74 AMENDMENT404, 4', ~ Docket No. 316 Page 5 of 11 (l) Deleted by Amendment 63. (m) Deleted by Amendment 19. (nf Deleted by Amendment 28. Amendment (o) Xndiana Power Company shall implement No. 12, 180 and maintain, in effect, all provisions of the approved as described in the Updated Safety Analysis Report for the facility and as approved in the dated June 4, 1979, subject to the following provision: The licensee may make changes to the approved fire protection program without prior approval of the Commission only , if those changes would not adversely affect the ability to achieve and maintain in the event of a fire. Amendment (p) Deleted by Amendment No. 64, 121, INDEX LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS TION ~PA 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIALFLUX DIFFERENCE .......................... 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR . 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO 3/4 2-13 3/4.2.5 PARAMETERS MODE 1 3/4 2-15 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ MODES 2, 3, 4 AND 5 3/4 2-17 3/4,2.6 ALLOWABLEPOWER LEVEL..... ~................. ~........ 3/4 2-19 3/4 3 INSTR MENTATION 3/4.3.1 SYSTEM INSTRUMENTATION .................... , 3/43-I 3/4.3.2 ENGINEERED SAFEIY FEATURE ACTUATION SYSTEM INSTRUMENTATION.........: . ~... 3/4'3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation ~........... 3/4 3-34 Movable Incore Detectors Seismic Instrumentation ..................... 3/4 3-38 3/4 3-38a Meteorological Instrumentation.................. 3/4 3-39 Instrumentation . 3/4 3P2 Post-Accident Instrumentation 3/4 345 Explosive Gas Monitoring Instrumentation............ 3/4 3-53 3/4.3.4 TURBINE PROTECTION 3/4.3-56 3/4.4 REA 0 COOLANT SYSTE 3/4.4.1 LOOPS AND COOLANT CIRCULATION Startup and Power Operation 3/4 4-1 COOK NUCLEAR PLANT-UNIT2 V AMENDMENT A, 4Q, ~ I INDEX LlhQTING CONDITIONS FOR OPERATION AND SURVEILLANCEREQVIREMINTS SECTION PAGE /4.8 LE I POWER SYSTEM 3/4.8.1 A.C. SOURCES Ope rating e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 8-1 S hutdown 3/4 8-9 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating . 3/4 8-10 A.C. Distribution - Shutdown 3/4 8-11 D.C. Distribution - Operating............ ~ ~ ~ ~ 3/4 8-12 D.C. Distribution - Shutdown ~ ~ ~ ~ t Q ~ 3/4 8-16 D.C. Distribution - Operating - Train N Battery System ~ ~ ~ 3/4 8-17 3/4.8.3 ALTERNATIVEA,C. POWER SOURCES ......................... 3/4 8-20 3/4.9 RE LING OPERATIONS 3/4.9.1 CONCENTRATION 3/4 9-1 3/4.9.2 INSTRUMENTATION 3/4 9-2 3/4.9.3 DECAY TIME...... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Q ~ 3/4 9-3 t. 3/4.9.4 CONTAINMENTBUILDINGPENETRATIONS ~ ~ 3/4 9Q 3/4.9.5 COMMUNICATIONS 3/4 9-5 COOK NVCLEAR PLANT-VNIT2 AMENDMENT444, 4' \ ' f INDEX BASES SECTION PAGE 3/4.7 PL T SYSTEM (Continued) 3/4.7.8 SEALED SOURCE CONTAMINATION B 3/474 3/4.8 ELE ICAL POWER SYSTEMS... B3/48-1 /4. REFUELING OPERATIONS 3/4.9.1 CONCENTRATION B 3/4 9-1 3/4.9.2 INSTRUMENTATION ...o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B3/49-1 3/4.9.3 DECAY TIME... \ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B3/49-1 3/4.9,4 CONTAINMENTBUILDINGPENETRATIONS B3/49-1 3/4.9.5 COMMUNICATIONS ........... B3/49-1 3/4.9.6 MANIPULATORCRANE .:.........,............. B3/49-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING .... B3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVALAND COOLANT.CIRCULATION ...... B3/49-2 3/4.9.9 CONTAINMENTPURGE AND EXHAUST ISOLATION SYSTEM B3/49-3 3/4.9.10 and 3/4 9.11 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL . B3/49-3 3/4.9.12 STORAGE POOL VENTILATION SYSTEM.................. ~..... B3/4 9-3 3/4.9.13 SPENT FUEL CASK MOVEMENT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/49% 3/4.9.14 SPENT FUEL CASK DROP PROTECTION SYSTEM ................, . B3/4%4 3/4.9.15 STORAGE POOL CONCENTRATION . B 3/4%4 3/4.10 SPECIAL EST EX EPTIONS 3/4.10.1 B 3/4 10.1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS ...... B 34 10-1 COOK NUCLEAR PLANT-UNIT2 AMENDMENT4P, 4', XV' 3/4 LIMFIINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMPiTS 3/4.3 INSTRUMENTATION Page Intentionally Deleted COOK NUCLEAR PLANT-UNIT2 Page 3/4 3-50 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.3 INSTRUMENTATION Page Intentionally Deleted COOK NUCLEAR PLANT-UNIT2 Page 3/4 3-51 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIRIMENTS 3/4.3 INSTRUMENTATION Table Intentionally Deleted COOK NUCLEAR PLANT-UNIT2 Page 3/4 3-52 AMENDMENTA, 44$ , 4' 3/4 LIMI'HNGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-11 Continued Table Intentionally Deleted COOK NUCLEAR PLANT-UNIT2 Page 3/4 3-52a AMENDMENT44$ , 4$ $ 6.0 ADMINISTRATIVECONTROLS 62 IZATI N Continued FACILITYSTAFF Continued

b. At least one licensed Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in Mode 1, 2, 3, or 4, at least one licensed Senior Operator shaH be in the control mom.

Co An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

d. AH CORE ALTERATIONS shall be directly supervised by a licensed Senior Operator trained or qualified in refueling and CORE ALTERATIONS (SO-CA) who has no other concurrent responsibilities during this operation.

'Ihe amount of overtime worked by plant staff members performing safety-related functions must be limited in accordance with NRC Policy Statement on working hours (). The Shift Supervisor, Assistant Shift Supervisor, and Unit Supervisor shall hold a Senior Operator License. go The Operations Superintendent must hold or have held a Senior Operator License at Cook Nuclear Plant or a similar reactor and one mid-level Operations Production Supervisor shall hold a current Senior Operator License.. The unexpected absence, for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, of the on-site individual qualified in radiation protection procedures is permitted provided immediate action is taken to fill the required position. COOK NUCLEAR PLANT-UNIT2 Page 6-2 AMENDMENT&, ~, 43$ 6.0 ADMINISTRATIVECONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Rev. 2, February 1978.

b. Deleted.

c. Deleted.

d. PROCESS CONTROI. PROGRAM implementation.

e. OFFSITE DOSE CALCULATIONMANUALimplementation.

f. Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974, and Regulatory Guide 4.1, Rev. 1, April 1975.

g. Fire Protection Program implementation.

6.8.2 Each procedure and administrative policy of Specification 6.8.1 above, and changes thereto, including temporary changes, shall be reviewed prior to implementation as set forth in Specification 6.5 above. 6.8.3 A plant program for post-accident sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze samples, containment atmosphere noble gas samples, and unit vent gaseous effluent samples for and particulates under accident conditions. The program will include the following:

a. Training of personnel,

b. Procedures for sampling and analysis,

c. Provisions for maintenance of sampling and analysis equipment.

COOK NUCLEAR PLANT-UNIT2 Page 6-13 AMENDMENTA, 488, 4VS, kV8 3/4 BASES 3/4.3 INSTRUMENTATION 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITYof the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident. 3/4.3, . EXPLOSIVE G S MONITOR G INSTRUMENTATION This instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the Waste Gas Holdup System. The and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant. 3/4.3.4 TURBINE PROTECTION This specification is provided to ensure that the turbine protection instrumentation and the turbine speed control valves are and will protect the turbine from excessive . Protection from turbine excessive is required since excessive of the turbine could generate potentially damaging missiles - which could impact and damage safety related components, equipment or structures. COOK NUCLEAR PLANT-UNIT2 Page B 3/4 3-3 AMENDMENTA, 44$ , 449, XV' 3/4 BASES 3/4.7 PLANT SYSTEMS 3/4.7.7 HYDRAULICSNUBBERS Continued included to ensure that the periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of service life. The requirements for the maintenance of records and the service life review are not intended to affect plant operation. The number of 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 functionally tested deviates from the number required by the Standard Technical Specifications (, Revision 4). A list of individual with detailed information of location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of . The accessibility of each 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 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 shall be made in accordance with Section 50.59 of . 3/4.7.8 SEALED SOURCE CONTAMINATI N The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for . Mis limitation will ensure that leakage from byproduct, source and sources will not exceed allowable intake values. COOK NUCLEAR PLANT-UNIT2 Page B 3/4 74 AMENDMENTA, &, 4Q, 444 9.8 S C S The Facility Service Syseems consist of the Fixe Procection Syscems, ehe System, and the Compressed Air System. 9.8.1 FIRE PROTECTION SYSTEM oduct o The infoxmation presented in Section 9.8-1 provides a general discussion of the various fire proeeccion systems at Cook Nuclear Plant. Xn addieion, references to specific documents have been provided to address different facets of the Fixe Proteceion Program+ in greaeer decail. These documenes 'Lre: o Fire Hazards Analysis. o Safe Shutdowa Capability Assessment (SSCA) . o Fixe Proeection Program Manual (FPPM). The Fixe Hazards Analysis providis a zone-by-zone analysis of the fixe hazards and the effects of a postulated fire at Cook Nuclear Plaae in accordance with the Branch Techni.cal Posieion APCSB 9.5-1. The SSCA provides a suaamLzy and che results of the analysis of the Cook Nuclear Plane to the requirements of , Sections XXX.G and L). Analyses have been performed foz the specific zequirements of Appendix R,.L (alternate shutdown), which confirm ehe capability to safely bring the reactor from full power operation to cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Specific NRC provide the basis for accepeance of Sections IIX.G, J, K, L, and 0 of Appendix R eo for which Sections XXI.G and IXI.O aze contingent upon ehe maintenance of administrative control of combuseibles equivalene to Sections XIX.K.1 through XII.K.8. +Refer to 9.8>>1 July, 1994 The FPPM provides a description of the overall fize protection program for Cook Nuclear Plant including major responsibilities of involved organizations. The FPPM also contains information about exemptions from the requirements of Appendix R to technical evaluations related to fire protection, NRC , miscellaneous analysis and evaluation summaries, and a fire protection design basis table which compares plant fire protection features against APCSB 9.5-1 Appendix A guidelines. es a e The fire protection system is designed to achieve the following objectives: a) Provide automatic fire detection in those areas where the fire danger is greatest. b) Provide fire extinguishment by fixed systems of the water, Halon 1301. or dioxide type and actuate automaticaI3.y or manually in those areas where the fire danger is greatest. c) Provide manually operated fire extinguishing equipment including fire hose reels capable of using water, foam, or dioxide as the fire fighting agent, and portable equipment of the wheeled and hand carried type for use by personnel at all points throughout the property. d) The fire protection system is designed to equal or exceed the standards of the National Fire Protection Association and the American Nuclear Insuzers. S te De adOe to The Fize Protection System is shown in Figures 9.8-1 and 9.8-2. 9.8-2 July, 1994 ATTACHMENT 4 TO AEP:NRC:0692CX COOK NUCLEAR PLANT COST BENEFICIAL LICENSING ACTION REMOVE UNIT 1 AND UNIT 2 FIRE PROTECTION REQUIREMENTS FROM THE LICENSES AND TECHNICAL SPECIFICATIONS L to AEP:NRC:0692CX Page 1 e st Be e c a ce s Act o Regulatory Requirement: requires fire protection measures. Effect of Requirement: Location of these requirements in the technical specifications require other additional resources for making T/S changes to support the and increases the potential for Licensee Events Reports. Rationale for Regulatory Change: Adopting the Standard Fire Protection license condition in the would conform to , 88-12, and 93-07 and would assure that changes "to the under the provisions of would not adversely affect the ability to achieve and maintain . Approximate Cost of Requirement: It is estimated that in the next 20.5 years about thirteen amendments to the Fire Protection T/S will not need to be filed and about twenty six Safety Reviews will be conducted. This results in a savings of about $ 114,400. Also, it is estimated that one unneccessary Licensee Event Report per year will be avoided. At $ 10,000 per LER, minus $ 1,600 for each reportability review performed for 20.5. years, this results in an additional savings of approximately $ 172,200. Thus the estimated total cost savings will be about $ 290,000.

AS

CRD

AB

RCP

H HO-

header

OPERABLE

OPERABLE

headers

high radiation areas

AF

HVAC

CO2

OPERABLE

OPERABLE

OPERABLE

inoperable

dampers

Cable Tunnel draac.'2 ~

Penetration

CO2

operable

inoperable

OPERABLE

OPERABLE

inoperable

OPERABLE

OPERABLE

OPERABLE

hydrostatic

ESP

ESP

OPERABLE

OPERABLE

acxoL, or 2) escab' a cinuous fixe wacch pacxoL on one side.

inoperable

inoperable

LS

OPERABLE

dampers

HELB

dampers

OPERABLE

operable

ShiM

reactor coolant

iodines

PMT

inoperable

overspeed

overspeed

snubbers

snubber

snubber

NUREG-0452

snubbers

10 CFR Part 50

snubber

snubber

snubber

CPR

LO

CPR

plutonium

CO2

surv 'Lance testing in the procecced area, the fire ecection system(s) require be OPERABLE by Specification 3.3.3. be'erified co be OPERABLE; lacion of an automatic CO s ession system temporarily puts chis syscem actuation mo che abiLS.

CO2

inoperable

inoperable

inoperable

inoperable

inoperable

headers

CCTVs

inoperable

inoperable

operable

inoperable

inoperable

CO2

inoperable

dampers

dampers

UPDATED FINAL SAFETY ANALYSIS REPORT

Indiana

Michigan

Fire Protection Program

SER

fire protection program

safe shutdown

NUREG-0612

NUREG-0612

DNB

REACTOR TRIP

Remote Shutdown

REACTOR COOLANT SYSTEM

REACTOR COOLANT

BORON

PENETRATION

BORON

PENETRATION

OPERABILITY

RESIDUAL HEAT REMOVAL

OR

BORON

SHUTDOWN MARGIN

reactor coolant

iodines

REMOTE SHUTDOWN

remote shutdown

control room habitability

General Design Criteria 19

10 CFR 50

REMOTE SHUTDOWN

remote shutdown

OPERABILITY

snubber

snubbers

snubbers

snubber

snubber

snubber

snubber

snubbers

snubber

inoperable

snubbers

snubber

snubber

inoperable

snubber

snubber

snubber

snubber

snubbers

snubber

snubber

snubber

high radiation area

snubber

snubbers

snubber

snubber

snubbers

snubbers

Westinghouse

NUREG4452

snubbers

snubber

10 CFR Part 50

snubber

snubber

snubber

10 CFR Part 50

Michigan

Fire Protection Program

SER

safe shutdown

SE

DNB

REACTOR TRIP

Remote Shutdown

OVERSPEED

REACTOR COOLANT

AL

BORON

BORON

OPERABILITY

BORON

SHUTDOWN MARGIN

OR

Generic Letter 82-12

reactor coolant

iodines

OPERABILITY

OVERSPEED

overspeed

OPERABLE

overspeed

overspeed

overspeed

snubbers

snubber

snubber

snubbers

snubbers

Westinghouse

NUREG4452

snubbers

snubber

10 CFR Part 50

snubber

snubber

snubber

10 CFR Part 50

plutonium

special nuclear material

Service Water

10 CFR 50, Appendix R (specifically

Section IXI

SERs

10CFR50,

transient

GL 88-12

10CFR50,

SERs

BTP

carbon

carbon

10 CFR 50, Appendix A

Fire Protection Program

UFSAR

GLs 86-10

Fire Protection program

10 CFR 50.59

safe shutdown

10 CFR 50.59