ML17320A487

Amends 71 & 53 to Licenses DPR-58 & DPR-74,respectively, Revising Surveillance Requirements for safety-related Snubbers & Adding Tech Specs on Surveillance Requirements for Inservice Insp & Testing of Components

ML17320A487
Person / Time
Site:	Cook
Issue date:	04/13/1983
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML17320A488	List: ML17320A487 ML17320A489 ML17320A490
References
NUDOCS 8304270198
Download: ML17320A487 (48)

Text

~o ~'~<co~

yV P

I+hQ "'

c

~=-"

o-.

W~*~+

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

71 License No.

DPR-58 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

B.

C.

D.

E.

The application for amendment by Indiana and Michigan Electric Company -(the licensee) dated November 11, 1981, as supplemented February 25, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in c'onformity with the application, the provisions of the Ach, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

8304270198 830413 PDR ADOCK 050003 1 5 P

PDR

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Faci lity Operating License No. DPR-58 is hereby amended to read as follows:

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

71, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Speci ficati ons.

3.

This license amendment is effective as of the date of its issuance.

F THE NUC REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance: April'3, 1983 j t ven A.

arga, Ch f Operating Reactors ch fl Division of Licensing

~

~

- ~

r

~ ~

~

ATTACHMENT TO LICENSE AMENDMENT AHENDl1ENT NO.

71 TO FACILITY OPERATING LICENSE NO.

DPR-58 DOCKET NO. 50-315 Revise Appendix A as follows:

Remove Pa es 3/4 0-2 3/4 0-3 3/4 7-27*

3/4 7-28 3/4 7-29 3/4 7-30 3/4 7-31 3/4 7-32 3/4 7-33 3/4 7-34 3/4 7-35 3/4 7-36 3/4 7-37 3/4 7-38 3/4 7-39 3/4 7-40 6-20 B 3/4 7-5*

B 3/4 7-6 Insert Pa es 3/4 0-2 3/4 0-3 3/4 7-27*

3/4 7-28 3/4 7-29 3/4 7-30 3/4 7-31 3/4 7-32 3/4 7-33 3/4 7-34 3/4 7-35 3/4 7-36 3/4 7-37 3/4 7-38 3/4 7-39 3/4 7-40 3/4 7-40a 6-20 B 3/4 7-5*

B 3/4 7-6

• Included for convenience

3/4.0 ='LIC='"- I:7 SURVEILLANCE R:-Q IR~TS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or ocher conditions specified for fndividual Limieiag Conditioas for Operation unless otherwise stated fax an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a, A, maximum allowable exeeasion aot to exceed, 25Z of the surveillance interval, and b.

A tota1 maadznun combined'time for aay 3 consecutive, surveillance intervals not to exceed 3.25 times the specified surveillance interval.

4.0.3 'erformance of a. Surveillance.Requirement within the specified tfme interval shall constitute compliance wieh OPERABILITY requirements for a Limiting Condition for Operation and.associated QCTION statements unless otherwise required by the specification.

Suzvefllaace requirements do aot have to be performed oa inoperable equipmeat,.

4.0.4 Entry into an OPERATIONAL MODE oz other specified applicability condi-'ion.

shall aoe be made unless the Surveillance Requirement(s) associated with the Limitiag Condition for Operation have beea performed withia the seated surveillance ~tezval or as otherwise specified.

44.0.5 Surveillance Requiremeats for insezvice inspection and testing of'SME Code Class 1, 2, and 3 components shall be applicable as follows:

Insezvice inspection of ASHE Code Class.1.,

2 aad 3

components and iasezvice teseing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed ia accordance with Section XI of the ASME Boiler aad Pressure Vessel Code aad applicable Addenda as required by 10 CPR 50, Section 50.55a(g),

except where specific written relief has been granted by the Commission pursuant.

to 10 CPR 50, Section 50.55a(g) (6) (i).

• Por Unit, 1 and untie. the Technical Specification can be revised to reference Section 4.0.5 or to specifically exempt certain actions or Surveillance Requirements from Section 4.0.5 requirements, this Section wiI1 apply only to Technical Specifications 3/4 7.8, 3/4 4.1 and 3/4 9.8.

D. C.

COOK - UNIT 1 3/4 0-2 Amendment t/o.

71

3/4.0 APPLICABILITY SURVEILLANCE REQUI~~NTS b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASHE Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler And Pressure Vessel Code and applicable Addenda Required frequencies for terminology for inservice performing inservice inspec-ins ection and testin criteria tion and testin activities Co At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 366 days The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

d.

Performance of the above inservice inspection and testing activities shall 'be in addition to other specified Surveillance Requirements.

e.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

D. C.

COOK - UNIT 1 3/4 0-3 Aaendment No.

71

PLANT SYSTE:tS SURVEiLLANCE REgUIRB1ENTS Continued)

1. "With a half-life greater than 30 days (excluding Hydrogen 3),

and b.

C ~

2.

In any form other than gas.

Stored sources not in use - Each sealed source shall be tested prior to use or transfer to another licensee unless tested within the previous six months.

Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.

Startuo sources - Each sealed startup source shall "be tested within 31 days prior to being subjected to core flux and following repair or maintenance.to the source.

4.7.7.1.3 Reoorts - A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days if source leakage tests reveal the presence of > 0.005 microcuries of removable contamination.

0.

C.

COOK-UNIT 1 3/4 7-27

~

0

~

~

0 0 0

0

~

0 ~

0

~ ~

~

0 0 0

~

0

~ I

~

~

Qt 0--

~ ~

0

~

~I 0

~ ~

0 0

~

~ 0 0

~

~

~ 0 0

~

~

0 0

11

~ 0 \\

ell ~ 0 0 0

0 000 0 0 0

~ ~

~ ~

0 0

~

~ 's

~ e

~

I~

~ 0

~

tie Ie 0

~

~

0 0

Il 0

~ \\

0 It 0

~

~

0 ~

~II

~

~

~

II 0

~

~

~

~

0

~ ~

0

~ I 0

~I 0 ~

~

nep 0

SMISI

~

~

ol 0

~ ~

0 0 0

~

~

0 0

~ e 0 0

~

~

I ~

0 It 0

~

0 tl

~

~

0

~

~

~

0 0

0 sl ~

~

0

~

~ 0

~ 0 e 0 ~

0

~

0 0 0 0 0 0 ~

~

tl 0 II 0 0

I ~ 0 U

a 00-tl 0 0 0

0

~

~

0

~ ~

~ 0

~ 0

~

~

~ 0

~ ~

~

0

~

~I

~

0

~

~

~

0

~

0 e 0

0

~

I ~ ~

0

~

0 0

~

0

~ 0

~ 0 I

~

~

II

~

0 0

~ ~

~ ~ 0 0

~

0 0 I'

II 0

~I 0

~

~

0 0

~

0 0

~

~ 0 II

~

~I ~

~ 0 Ie

~ ~

~

0 0 000

~

~

0

~

~

II

~

~

~

~ ~

~ ~

0

~ I

~

0

~I

~

0 0

~

~ "

v ~

0 0

~I

~

~

0 0

~ 0 0 0 0

0

~

0

~

~ 0

~ -

- ell

~ - ~

~

0 0 0

~

0 0 ~

~

0

~

~

~

~ 0 II

~

0

~ 0 0

~ 0

~

~ 0 0

~

- el ~

~

~

~

~

~

0 0

~ ~

~

0

~

0 0

~

0

~

~ 0 0

~ 0 0 0

oil Ill~ 0 0 0 0

~

0 I ~ e

~

~

~

~

~

0 0

~I 0

~

0 0

0 0

tr

~ 0 0

~

0

~ 0 ~ 0

~

~ 0 I~

~

~ ~

~

~

~

0

~

0 ~

II ~

0

~

0

~

~

0

~ 0 0

~ 0 r 0

~

~

~

VP 0 ~

0 I~ I

~

~ ~

e r

~ 0

~

~ ~

e

~ I

~ 0

~

0 ~

0 0

~

II I ~

II 0

~

~ 0

~

0

~

0

~ I I I 0 0

~

~

~

~I ~

~

~

'I ~

~

0 0 0

~

0 Wile 0

0

~I 0

0 0

I ~ r II

~

~

0 II I 0 ltel 0

0 0

~lo

~

~

~ 0 0 ell 0

0 0

0 I~ 0 0

0 0 ~

0 ~

~

~

~

0

~ 0 0

0

~

~

~

0 0

~

~

I 0

0 0 0

II ~

0 0

~

0 0

0 ~

0 0 0

~

0 0 0 0 0

~

~ ~

0 0

~

0 0 0 ~

~ ~

0 0 0 0 0

~ 0

~

0

~I 0

~

~

0 0 0

0 0

~

~

0 II 0 0

~ 0

~

~

I ~

0

~

0 0 II 0

Il

~

~

~

~I 0

0

~

~ I 0 0 VO 0 0

~ 0

~I 0

~

~l 0 ~

~ 0 ~

~

~

~ 0

~

0

~

0

~

0 I ~

~

0 0 III I 0 ~

~

0 ~ 0

~ ~

0 0 0

~

0

~

~

~

~ ~

~

OI100

~

~ 0 0

~

0 0 0

~ 0 0

~

~ ~

~

0 0

0

~

0 0 0 Ills 0

~ ~

~

~

~

0

~

0 0 ~

~

~

~ 0 0 ~

~

1

~

0 0

~

~

~ 0

~

~

0

~

~ ~

<<01 ~ 0 0 ~

0 ~

~

0 0

01 ~ I ~

0

~

0

~

0

~

~ ~

0

~

0

~

0 0

~

~

~

0 0 0

~

~ 0

~

0 DI~

0 0

~

0 0

0

~

01 1 ~ I ~ ~

~

~

~I 0

~

~

II

~

~

~

~

~ ~

0

~

~

11 0

~

II 0

~

0 0

0

~

0 0

~

~

0

~

0

~ ~

0

~

~

0 0 0 0 ~

~

0 0 0

~

~

0

~

0 0

~

0

~

0 0

~

I ~

0 0

~

00

~

~

~

(D TABLE 1

eee D

Gi GOOK PLAall Util l 1

I SAFET RELATED HYDRAULIC SNUBBERS~

StaUBBER tlO O

7CI We C+

HANGER W.BK NO 1-GRG-S519 1-GRG"S53$

SYSTEM SNUBBER INSTALLED ON LOCATIOII AIID ELEVATION REAOYCR GooLAHT

. ELKV.683'-.

5 1/2 IH PRESSURIZER ENCLOSURE REACTOR COOLANT AZ 25 ELEV. 610'->U BKYwEEH 8YEH.

GEN. No.

1 i No RC PullP No.

1 ACCESSIBLE OR INACCESS IBLE.

H IGH RAO IATIOtl LotIE ESPFC IALLY 0 IffICULT TO REIQYE I,

1-GRG-S538 1-GRG"S555 REAcTCA GooLANY Az 41 ELKv. 614'-10" BKLCM 8Tll~

GEN. No. I REAOTCA GooLANY Az 141 ELEV~ 614l~2~

BELOM STtl GLN No 2

No eeel I

1-GRG-5562 REACTOR COOLANT Az 154 ELKv 010 5

SETNEEN sYllo GEN+

No 2 ANo RG PUHP Noi 2 Nn 1-GRG-S564 REACTOR COOLANT AZ 31/

ELEv. 614'-10 1/8" aELOM sm.

GEN. No. tl t(o 1-6RG-S5o6 RKAOYoa COOLANT Az $32 ELcv 610'-5" acTuEEH sTtl GEN ~ No 4

ANP RG PUNP No+

O 1-GRG-S5'Q REAcTCA Coca.AHT Az 223 ELKV. 614'0 1/8" SELCM sYllo GENo Noi

~

O oO I

10 11 I

StlUBBER NO HANGER

~RK~tiO 1-GRG-S575 1-GRG-S582 1-GRG-S587 ue I ~

4UOA I'LANI <<unt I I

j ~~E3.7-SAFETY RELATED SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION RKAOTCR Gool.ANT Az 208 ELKve 610 <<5 QETltEKN STtI ~

GKN ~

NO ~ '$ ANP RG PUttP NOe t

REAcTCR GooLANT Az 212 ELKv. 617'-4" NK*R REAOTCR GAVITT MALLt ACROSS FROM Sme GKN. NO. 5 RKAcTCR C00LANT Az 260.

ELKv 622'-4 1/4" IN.

GONTAINttENT HYDRAULIC SNUBBERSi

~8 ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFF IGULT J

~

ZONE TO RENOVE No 1-GRG-S592 REAOTCR GCCLANT Az 292 ELEV. 68>t-6 >/4 IN PRESSURIZER ENCLOSUREe N

1$

I 1-GRG S594 I-GPG-S596 REAcTCR C00LANT Az 292 ELEv 691'-9" Itl PRESSUR I ZER ENCLOSURKe REAcTCR GooLAN r Az 285 ELKV. 691'-9" PRESSURIZER ENCLOSURCe N

N GRQ S598 REAOTCR GooLAHT Az 292 ELEV 670t-P $/4N IH PRESSURIZER EtlCI.OSUREe 16 O

1-GRG-S599 RKAGTQR GCCLANr Az 287 ELcv. 672'-4" IN PRESSURIZER ENCLOSURKe No

~ )

~

Do. C COOK PLANT - UN I T 1 I

TAa.

c'. 3. -4 SAFETY RELATED HYDRAULIC SNUBBERS Cl OO I

SNUBBER

~NO 17 18 HANGER

~MARK NR 1<<GRC-S604 1-GRC"S608 SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION RKAcTQR CooLANT Az 286 ELEv. 688 -10" 'IN PRESSURIZER ENCLOSURKo RKAcTCR CQOLAHT Az 286 ELrv. 693'-0U IN PRKSSURIZKR ENCLOSURKo ACCESSIBLE OR HIGH RADIATION

~

No ESPEC IALLY 0 IFF ICULT TO RENOVE No

~

oo 1-GRC-S614 REAcTCR CooLANT Az 282 ELEv. 681'-0H IN PRESSURIZER ENCLOSURE+

N

~

I

20 22 1-fM-S1 1-rW-S2(L) 1-~S2(u)

FKKouATKR Az $1 FLEv 6>4'U BEHIND STII GEN ~ Noi 1 FEKDMATKR Az 26 ELrv. 6-6H BEHIND STII~

GEN. No 1

FKKO'WATER Az 26 ELKS 6/6~M BKHIND Sth GEN ~ No 1

~

~

No N

I I

No N

No

~

~ >

n) io 2$

~

1-FH"SQ FEEDMATER AZ 20 ELcv+ 629'-9" BEHINo STIIY GENT No ~

1 O

24 1-FH-S4(L)

FEKowATER Az 154 ELKv~ 6>6'A >/8H BEHIND STIIY GEN. No~ 2 No

~ g

~

~

Oo Go COOK PLANT -IUNIT 1

~3-4 SAFETY RELATEO HYORAULIC SNUBBERSi SNuBBER

~NO HANGER

~RK~NO SYSTEN SNUBBER INSTALLEO ACCESSIBLE OR

'HIGH RAOIATION INACCESS IBLE

. ~

ZONE

'ESPEC IAUY 0 IFF ICULT TO REl%VE OO I

Ae C+

25 1-Fws4(u)

FccpwATKR Az 1544 ELKV.'6tlO'A3/8" BKHlHO Smo GKH~

Noo 2

~ o No No 26 1-rw-s5

'FccowATKR Az 163 ELKvo 634 ~9 BKHJHp STtt ~

GKN~ No ~ 2

~ I I

27 1-FH-S6 FKKOMATKR Az 157 ELKVe 629'-9" BKHtHD GKH ~

No ~ 2 Smo CD I

I'D I r+

O 28 29 1-FQ-S7 1-F~SS(L) 1-~s8(u) 1-FQ-S9 1-F~S10(L)

FKKOMATKR Az c04 ELKv~ 634 -9" BKHtHD STgo GLH ~ No.'3 FccowATKR Az 200 ELKVo 633 A BKHItlp STNo GKH No, 3 Fcco'lJATKR Az 200 ELKVo 636 W BKHlHO STtlo GKH~ No. 3 FccowATKR Az 1944 ELKVo 629'-9H BKHIHD STgo GKH. No. 3 Fccou*TKR Az 3344 ELKV~ 633 A BKHIHD STtfo GKH~ No ~ 4 I ~'

~I No N

No I.

~

~

~

4 ~ ~

~ I

~

~

I D. G.

COOK PLANT - UNIT 1 I

4 4

4.7-4 I

SAFETY RELATED IIYDRAULIC SNUBBERS~

n OO I

Io SNUBBER NO.

HANGER

~RK NO..

1-FM-Sio(u)

SYSTEH SNUBBER INSTALLED ON LOCATION AND ELEVATION FEEDMATKR Az $34 EI.KVe 636'-OH BEHIND STII~

GLN. No. 4 ACCESS IBLE OR

'HIGH RAD IATION

'SPEC IALLY 0 IFF ICULT INACCESS IGLOO

~

ZONE TO REI'DVE Nn 1-FM-S11 1-Flk.S12 FEEDMATKR Az 330 ELKVe 634 9

BCH IHO STII~

GEN No 4

FEKDNATER Az.$43 ELEve 629'-9" BEHIND STII~

GKN. No 4

N O

41 1-GGS-S634 1-GCS-S637 IWCS"S7$7 1<<HSS-2 1~5-3 CHEII&VoL,CONTROL Az 292 ELEVe 613'N CONTAINHENT CHKH&Vo'L,CONTRoL Az 71 ELEve 608I>>10H IN ANNULUSe I

RG PUHP SEAL QATKR SUPPLTI BKTMEEN RC PUNP No ~ 2 AND CRAHK +ALL~

IMMEDIATELY UNDER aRATINo Az 128 ELKV 612'-7 1/SH HAIN szcAII Az 8 ELEVe 639'-1 I/4" QKTllEEN STII GEN ~ No. l AND Noe 4 HAIN sTEAN Az 17 ELcv. 635'ETuccN STIIY GEH. No.

1 Awo No 4

HAIN $TKAII Az 172 ELcv. 639'-1 1/4" BEHIND STII~

GKN No 1

j 4

Y s Nn No N

I~

TAUPE 3 I-4 Oo Co COOK PLANT-UNIT 1 I

SAFETY RELATED HYDRAULIG SNUBBERSi s

Qlnn C+

SNUBBER HANGER NO QAAK ~NO 42 1-&S-4 43 1-MSS-6 SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION HAIII STKAH AZ 165 EI.Kvo 635 BETWEEN STH GENT Hoo P-AND HOog f4IN sTEAH AZ 191 4.EVo 635 BKTMKKN STHoGENeNOe2 AND Hoop HAIN STKAH Az 184 ELKV 639'-1 1/4N sKTuKKN sTII~

GEN ~ No. 2 AND Noi 3 N

No

~

lI ACCESS IBLE OR

'LIGH RAD IATION ESPEG IALLY D IFF IGULT J

'"'ONE TO RE %VE 45 1-NSS-7 1-ASS-8 HAIN sTEAH Az 349 EI.Evo 635 BKNIND STHoGENeNO ~ 1 AND Noe4.

HAIN STEAH AZ 356 ELEve 639'-1 1/4" OETuEEN STH GENT No.

1 ANo No. 4 47 1-GCGM-S278 Cow o NKNT CooL I NO MATER EL.EVo 609'N 'CGM PUHP ARKA No 49 51 48 O

50 1-GCCM-S309 1-GGGM-S837 1-GCGM-S838 1-GCGM-3839 COHPONENT Cool. INO WATER ELEV 597'-1 'i/8N IN PASSAOElIAT NEAR sAHPI INo RooH Aux. BLDoi GOHPONENT COOLINO MATER ELEyo 621 Mu IN CCW puHp AREA COHPONENT COOL INO MATER ELKv. 621'-0" IN GGM pUHP AREA COHPONENT CODLING WATER El.Evo 621'-0" IN GGM PUHP ARKA N

No No

Do's GOOK PLANT

)UNI'T 1' 3n00 I

~ C+

SNUBBER NO 52 HANGER

~ARK NO 1-GGGW-S8II0 1-GCCW-S841 SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION GOIIPOHENT GOOLIHO WATKR ELEV. 621IMH IN CCW puttp. AREA

'CONPO HEHT Coo i I HO WATER EI Kvo 62'I MU IN GCM PUHP ARKA

~3 SAFE Y RELATED HYDRAULIC SNUBBERSi

~

~

ACCESSIBLE OR HIGH RADIATION.

ZONE ESPEC IAL'LY D IFF ICULT TO RENOVE N

54 55 1-GCO(S-S842 1-GCGW-S844 CotIPOHKNT GOOLINO MATER ELEva 621 -0" IN GCW Puttp AREA COHPOHENT COOLIH4 WATER EIKvo 609'-0" IH 'CCW Putip'REA No No No

~

'56 57 1-GBD-S56$

1-GBD-S569 58 1-GBD-557$

STtIO GEN ~

BLoWDoWN Az 277 ELEvo 608 W 1/2 IN ANNui.us STtto GENT BLowoowN Az 278 ELEV. 608 -6 1/2H IN ANNULUS STII~ GKII~ BLowoowN Az 181 ELKvo 607'-10 1/2" IN ANNUI.US A

c At N

No:

No 0

59 60 61 1"GBO-S574 1-GRH-57A 1-GRH-S7B STtlo GENo BLowDo'wN Az 181 ELKV. 607t-10 'I/2H IH AHNULUs RES I DUAL HE AT RKIIOVAL ELKvy 581 t-8 1/2" IH I-E RHR PUtiP R4oti 1IKSIDUAI HEAT REtIOVAL ELKV.'581t-4U IN I-E RHR PUHP ROON A

A' No No

~

~

No

U, I ~

I'vugg rLRnI uN>>

.OLE 3.7-4 SAFET RELATED HYORAULIC SNUBBERS~

C)

OO I

SNUBBER RO 62 HANGER

~MARK

'0 1-GRH-S47 SYSTEN SNUBBER INSTALLEO ON LOCATION ANO ELEVATION RESIDUAL HEAT REHOVAI Eggy 581~

IN I-M RHR PUHP ROOH ACCESSIBLE OR INACCESS ISLE HIGH RAO IATION ZONE ES PEG IALLY 0 IFF ICULT TO REI'SVE I

00 O

64 65 66 67 69 1-GRH-S48 1-GOG"S1$

1-GOG-S14 1-GS I-S103 1-GS I-S128 1-GSI-S575 1-GS I-S657 1-GS I-S707 RESIDUAL HEAT REHOVAL ELcv 580'A'l IN I-M RHR PUHP ROOH I-AB EHERa. OIcerL ExIIAUeT ELEv 596'-7 5/8N I-AB EHCRO. OIESEL ExNAUST ELcvi 60$ '-6N SAFETY INJECTION ELcv 57/I IN I<<E RHR PUHP ROOH SAFCTY INJECTION ELrv. 57$'N I-E RHR PUHP ROOH SAFETY INJEGTION ELcv. 598'-9 $/8N Az 664 IN ANNULUS shl KTY INJcc "IDN Az 185 ELEva 610'-0" IN ANNULUs SAFETY INJKOTIDN Az 228 ELEv. 608'-4 7/8" BEHIND RC PUHP No..k I

A No N

No No No Ycs Ycs No No

~

~

TABL Oo Go COOK PLANT ~ UNIT 1 I

SAFETY AELATEO HYORAULIC SNUBBEASi SNUBBER

~NO

~

71 HANGER QLRK ~NO 1-GGTS-S7XE)

SYSTEN SNUBBER INSTALLEO ON LOCATION AND ELEVAT10 CONTAIHNEHT SPRAY.

ELCVo 582t-0" IH I-E GONTAINtlENT SPRAY PUtIP RootI ACCESSIBLE OR HIGH RAOIATION ESPECIALLY DIFFICULT J

"'"'ONE TO AENOVE N

~ 72

~ 1-GGTS-S7$ (W)

GONTA IHtIEHT SPRAY ELEv 582IM IH 'l<<E GOHTAINNENT SPRAY PUNP RootI No 7$

'1-GGTS-S76(B)

GONTAINtIEHT SPRAY ELKS 579'-6" INSIDE LKAK OETKOTOR BOX'IPE CHASE

'4 1-GGTS-S76(A)

CONTA IutIENT SPRAY EI,Evo 579t&

INS I OK LEAK OKTECTOR BOX'IPE CHASE No 75 76 1-GGTS-S160A CONTAINMENT sPRAY (N)

ELcvo 582 W INBIQK LEAK OETEOTOR BOX'IPE CHASK 1-GGTS-S160A GOHTAINtlENT 8PRAY (S)

ELcvo 582t-0" INSIoc I.EAK OcTcoTCR Box'IPE cHAsc N

No

'0 77 78 1-GCTS"S161 (W)

GONTAINNENT SPRAY ELcv 579'-6u IH I

W CONTAINMENT SPRAY PvtIP ROOII 1-GCTS-5161 COHTA IutIENT SPRAY (E)

ELcv 579'AN IN I w GOHTAIHtIEHT SPRAY PUtIP ROOII N

~ ~

, ~

~

~

j o

~

O,C, COOI( l'LAI'IT-UNIT NO 1.

ABLE 3

SAFE ELA EO I OAAU C S UBOE S+

SNUBBER

~n~

lIANGER HKI~Di SYSTEH SfIUBBER ON OCA AN lNSTALLFD EEA 0

ACCESS IBLE OR lllGIl RAOlhTION HACCESS B

ESPEC IALLY DIFF ICULT 0 AEI'10VE OO I

rt

<<\\

I 1~

<<~

I CI 79 so

~ 82 84 85 N/A N/A N/A II/A N/A N/A STEAH GKIIERATOR EI.EV. 66!f!~

Ho+

1 STEAH GEtIERATQR Nof 1 EI.EV 66!it ~

STEAH GEIIKRATOR No ~

1 EI.EV. 665!

STaAH GEIIERATOR No>>'

EI.EV. 665>

STEAH GEIIERATOR Ho ~ 2 Et.r.v. 665! ~

STKAH GKIIERATOR No ~ 2 EErv 665! ~

STEAH GENERATOR NOf 1 ELEvo 665! ~

~

No YK Y s YKs Y s 86

. H/A STEAH GEIIERATOR EI.EV. 66!i'~

Ho, P H/A STKAH

.EI.Eve GKIIERATOR Ho, $

66!i!

f

~

Yes

. O 88 89 I H/A

~ N/A STEAH GEI!ERATOR Ho+

EI.Ev. 66."if' STKAH GKIIKRATOR Nof EI.KV, 665I, No YEs Y s

~

~

~

' 0 a.c.

COOK PLANT - UNIT No. 1 ALE 3./-4 SA E

EL 0

AAU C S 'UOOE SOBBER HANGER kfKEL o

9P N/A SYSTEN SNUBBER INSTALLEO ACCESSIBLE OR OC CCESS 0

STKAH GKNKRAl'OR NO ~

E).cv+ 6)i5)i HIGH RAOIATIN ESPECIALLY DIFF ICULT AEMO 91

~

93 94 N/A N/A N/A N/A slKAH GKNKAAl'oh No ~ 4 ELKv

• 665) ~

Sl'KAH GKNKRAl'oh No ~ 4 ELcv 665> ~

sl'KAH GKHKRAToh No ~ 4 ELKV~ 665) ~

slcAH GKNKRhl'oh Noi 4 ELKvo 665) ~

N I

CD I

Snu ers may e a e

to sa ety related systems without prior License Amendment to Table 3.7 4:

provided that a revision to Table 3.7-4.

is included with the next License Amendment request.

Modifications to the "High Radiation Zone" column due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table 3.7-4i is included with the next License Amendment request.

~

~

ADMENISTRATIYE CONTROLS c.

Records of.-radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

e.

Records of transient or operational cycles for those facility components identified in Table 5.9-1.

f.

Records of training and qualification for current members of the plant staff.

g.

Records of in-service inspections performed pursuant to these Technical Specifications.

~'.

Records of'uality Assurance activities required by the QA Manual.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR SO.59.

j.

Records of meetings of the'PNSRC and the NSDRC.

~ k.

Records for Environmental Qdalification which are covered under the provisions of oaraaraph 6.13.

1-Records of the service lives of hydraulic snubbers listed on Table 3,VW including the date at which service Life commences and associated installation and maintenance

records, 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be. prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations 'involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1. In lieu of the "control device" or "alarm signal".required by paragraph 20.203(c)(2} of 10 CFR 20:

ao A High Radiation Area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be bar ricaded and conspicuously posted as a High Radiation Area and entrance thereto shall. be controlled by issuance of a Radiation York Permit and any individual or group of individuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously in-dicates the radiation dose rate in the area.

D.

C.

COOK-UNIT1 6-20 Amendment No.

?1

PLANT SYSTEMS BASES 3/4.7.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room emergency ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions.

The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation. exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.

This limitation -is consisten with the requirements of General besign

.Criteria 10 of Appendix "A", 10 CFR 50.

3/4.7.6 ESF VENTILATION SYSTEM The OPERABILITY of the ESF ventilation system ensures that radio-active materials leaking from the ECCS equipment within the pump room.

following a LOCA are filtered prior to reaching the environment.

The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses.

3/4.7.7 SEALEO SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that

'the total body or individual organ irradiation does not exceed allowable'imits in the event of ingestion or inhalation of the probable leakag from the source material.

The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.

guantities of interest to this specification which are exempt from the leakage testing are consistent with the criteria of 10 CFR Parts 30.11-20 and 70.19.

Leakage from sources excluded from the requirements of this specification is not likely to'represent more than one maximum permissible body burden for total body irradiation if the source material is inhaled or ingested.

'D.. C.

COOK-UNIT 1

B 3/4 7-5

0 BASES (Continued) 3/4. 7. 8 HYDRAULIC SNUBBERS i

All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety elated systems is maintainec during and following a seismic or other event initiating dynamic loads.

Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then. only if their failure of failure of the system on which they are installed, would have no adverse effect on any safety-related system.

I The visual inspection frequency is based upon maintaining a constant level of snubbez protection to systems.

Therefore, the zecpxized inspection interval varies inversely with the obsezved snubber failures and is determined by the number of inoperable snubbers found during an inspection.

Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.

However, the results of such early inspections performed before the original recpdxed time interval has elapsed (nominal time less 25%)

may not be used to lengthen the recpxired inspection interval.

Any inspection whose results required a shorter inspection interval wi11 ovezxide the previous schedule.

N

'I When the cause of the rejection of a snubber is clearly established and zemedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable.

Genezically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, oz axe sixd.larly located or exposed to the same envizonmental conditions such as temperature, radiation, and vibration.

When a snubbez is found inoperable, an engineering evaluation is performed, in addition to. the detexmination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversly affected by the inoperability of the snubber.

The engineering evaluation shall determine whether or not the snubber mode of failure 'has imparted a significant effect or degradation on the supported component or system.

T-prwide assu--~cc -" snuc~ ~unctional zel-abil~ty, a rcpresentat-'ve sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals.

Observed failures of these sample snubbers shall require functional testing of additional units..

The service life of a snubber is evaluated via manufactured input and infoxmation through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal

replaced, spring replaced, in high radiation area, in high temperature

area, etc...).

The repxirement to monitox the snubber. service life is included to I

ensure that the snubbezs periodi,cally undergo a pexfoxmance evaluation in view o$ theiz age and operating conditions.

These records willprovide statistical bases. for future consi.dezation of snubbex service life, The requirements foz the maintenance of records and the snubber service life review are not intended

'o affect plant operation.

D.C.

COOK - UNIT 1 B 3/4 7-6 1

Amendment No.

71

1

~p,R RKQp(

Ga 9

'~p QW

+**++

UNITED STATES NUCLEAR REGULATORY COMM(SSlON WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 53 License No.

DPR-74 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated November ll, 1981, as supplemented February 25, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954 as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in con formity with the application, the provisions of the Act,'nd the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment.

and paragraph 2.C.(2) of Facility Operating License No. DPR-14 is hereby amended to read as follows:

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

53, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FO THE NUC REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 13, 1983 teven A. Varga, Chi f Operating Reactors nch

<1 Division of Licensing

~

~

~

~

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT'NO. 53 TO FACILITY OPERATING LICENSE NO.

DPR-74 DOCKET NO. 50-316 Revise Appendix A as follows:

~RP 3/4 0-2 3/4 7-19a*

3/4 7-20 3/4 7-21 3/4 7-22 3/4 7-23 3/4 7-24 3/4 7-25 3/4' 3/4 7-27 3/4 7-28

'/4 7-29 3/4 7-30 3/4 7-31 3/4 7-32 3/4 7-33 3/4 7-34*

6-20 B 3/4 7-5 B 3/4 7-6 B 3/4 7-7 B

B B

Insert Pa es 3/4 0-2 3/4 7-19a*

3/4 7-20 3/4 7-21 3/4 7-22 3/4 7-23 3/4. 7-24 3/4 7-25 3/4 7-26 3/4 7-27 3/4 7-28 3/4 7-29 3/4 7-30 3/4 7-31 3/4 7-32 3/4 7-33

-3/4 7-34*

6-20 3/4 7-5 3/4 7-6 3/4 7-7

• Included for convenience

1 Ip

~

~

3/4.0 APPLICABILITY SURVEILLdu.ICE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable duriag the OPERATIONAL MODES or other conditions specified for individual Lied.ting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a.

A maximum allowable extension not to exceed 25X of the surveill-ance interval, and b.

A total mandmum combined time for any 3 consecutive suzveill>>

ance intervals aot to exceed 3.25 times the specified surveillance interval.

4.0.3 Perfonnance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limit-iag Condition for Operation and associated ACTIQN statements unless otherwise required by the specification.

Surveillance zequirements do not have to be performed on iaoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified applicability condition sha11 not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveil-lance iaterval or as otherwise specified.

4.0.5 Surveillance Requirements for insezvice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:

a ~

Inservice inspection of ASME Code Class 1, 2, aad 3 components and iaservice testing of ASME Code Class 1,

2 aad 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CZR 50, Section 50.55a(g),

except where speci-fic written re1ief has been granted by the Commission pursuant to 10 CPR 50, Section 50.55a(g) (6) (i).

D.C.

COOK - UNIT 2 3/4 0-2 Amendment No.

53

PLANT SYSTEM SURVEILLANCE REOUIREMENTS Continued 3.

. Verifying that the standby fan starts automatically on a

Containment Pressure--High-High Signal and diverts its exhaust flow through the HEPA filters and charcoal adsorber banks on a Containment Pressure High-High Si gnal.

e.

After each complete or partial replacement of HEPA filter bank by verifying that the HEPA filter banks remove

> 994 of the OOP when they are tested in-place in accordance. with ANSI N510-1975 while operating the ventilation system at a flow rate of 25,000 cfm + lOX.

f.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 25,000 cfm + 10%.

~ sV.

0.

C.

COOK - UNIT 2 3/4 7-19a

PLANT SYSTEMS 3/4. 7. 7 S&aaBBERS LIMITINGCONDITION FOR OPERATION 3.7.'I.l All snubbers listed in Table 3.7-9 shall be OPERABLE APPLZCABILITYx MODES 1, 2, 3 and 4.

(MODES 5 and 6 for snubbers located on systems received OPERABLE in those MODES).

~

~

~

~

ACTION:x With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.7.1c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE RE UZREMENTS 4.7.7.1 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the repxirements of Specification 4.0.5.

a.

Visual Zn ections Subsmpxent Visual Ins ection Period*"

The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of commencing POWER OPERATION and shall include all snubbers listed in Table 3.7-9.

Zf less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months + 25% from the date of the first inspection.

Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:

No. Inoperable Snubbers er In ection Period 0

2 3~4 5,6,7 8 or more 18 months J 25%

12 months

+ 25~

6 months + 25%

124 days

+ 25@

62 days t 25%

31 days g 25%

The snubbers may be categorized into two. groups:

Those. accessible and those inaccessible during reactor operation.

Each group may be inspected independently in accordance with the above schedule.

I!

II The inspection interval shall be lengthened more than one step at a time.

The provisions of Specification 4.0.2 are not applicable.

DC Cook-Unit 2 3/4 7 20 Amendment t<o. 53'

~ SYSTEM

-~

SURVEZLLANCE RE UZRE~NTS (Continued) b.

Visuhl Znsnection Acceptance Criteria Visual inspections shall verify (1) that there axe no viszble indications of damage or impaired OPERABZLZTY, (2) attachments to-the, foundation or supporting structure are secure, and (3) in those locatioizs where snubber moveient can-be manually induced without disconnecting the snubber, that the. snubber has freedom of movement and is. not fxozen up.

Snubbers which appear inoperable as a zesult of.visual inspections may be determined OPERABLE for the purpose of establishing the. next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptibleg and (2) the affected snubber is functionally tested in the as found condition and determined OPZBABLE per Specification 4.7.7.1.d as appLicable However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber sha11 be detezmined inoperable'nd cannot be detezmined OPERABLE via functional testing for the puzpose of establishing the next visual.

inspection interval.

All.snubbezs connected to an inoperable common hydrauLic fluid reservoix shall be counted as inoperable snubbers.

c.

Functional Tests At least once pez'8 months during shutdown, a representative sample Q0% cd! the total of each type of snubber in use in the plant shall be functionally tested either in place or'n a bench test.

For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.7.1.d. ap additional 10% of that type of snubber shall be functionally tested).

The representative sample selected for functional testing shall include the various configurations, operating environments and. the range of size and capacity of snubbexs.

At least 25% of the snubber's in the representative sample shall include snubbers from the. following three categories:

1.

The first snubbex 'away from each reactor vessel nozzle 2

Snuhbers within 5 feet of heavy apxipment (valve, pump, tuzhdme, motor, etc

)

3.

Snubbers within 10 feet of the discharge fzom a safety relief valve Snubbers identified in Table 3.7-9 as "Especially Difficultto Remove" or i'n ".High Radiation Zones During Shutdown" shall also be included in the representative sample.+

• Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was perfozmed to cpxalify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent

date, D C Cook-Unit 2 3/4 7 21

+iendmeng

[(p.

53

PLY SYS~Z

- ~

SUÃ7E~~CZ RE UZR=-~S (Cont'ued)

Zn addition to the regular sample, snubbers which failed the previous.

functional test shall be retested during the next test period.

Zf a spa e snubber has been installed in place of a failed snubber, then both the failed snubber (ifit is repaired and installed in another position) and the spare snubber shall be retested.

Test results of these snubbm may not be included for the re-sampling Zf any sxnxbber selected for functionaL testing either fails to lockup or fails to move, i.e., frozen in. place, the cause will he evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested.

This testing recpxix'ement shaLl. be independent of the rapxirements stated above for snubbers not meeting the functional test acceptance criteria.

Por the snubber(s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber(sf.

The purpose of this engineering evaluation shall be to determine if,the components supposed by the snubber(s) were adversely affected'by the inoperability of the snubber(s} in order to ensure that the supported component remains capable of meeting the designed service.

H ulic Snubbers Punctiona1 Test Acceptance Criteria The hydraulic snubber functiona1 test shall verify that."

l.

Act~tion ~stra~xg action} is achieved within the specified zange of velocity or acceleration in both tension and compression.

2.

Snubber bleed, or release rate, where recpuxedg Ls wxthixl the specified range in compre'ssion or tension.

Eoz snubbers specifically rapxired to not, displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

e.

Snubber Service Life Monitorin A record of the sezvice life of each snubber, the date at, which the designated service Life commences and the installation and maintenance records on which the designated service life is based shall be. maintained as repaired by Specification 6.10.2.

Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Table 3.7-9 shall be reviewed to verify that the indicated service life has not been exceeded or willnot be exceeded prior to the next scheduled snubber service life review.

Zf the indicated service life will be exceeded prior to the next scheduled snubber sezvx.ce life review, the snubber service life shall be reevaluated or the snubber shall be replaced or -reconditioned so as to extend its service life beyond the, date of the next scheduled service life review.

This reevaLuation, replacement or reconditioning shall be indicated in the records.

D C Cook-Unit 2 3/4 7-22 Amendment tlo. 53,

TABLE 3.7-9 SAFFTY RELATED HYDRAULIC SNUBBERSi PIIUBBER NO o0 1

I 2

HANGER-QA~R(~

2-GRC-S537 SYSTEN SNUBBER INSTALLED ON LOCATlON AND ELEVATION REACTOR COOLANT AZ 25 ELEvr 6 l0 <<5 STH GEN ~ Noi 1 2-GRG-s538 REAcTQR cooLANT Az 41 ELEv 614<<<10N RG PUNP No+

1

. ACCESS IBLE OR HIGH RAO IATION ZONE

~ NO ES l:SPEC)ALLY D If F ICULl TO REtQVc'O v

5 I

LJ 2-'GRC-S555 2-GRC-S562 2-GRC-S564 2-CRC-S566 2-GRC-S573 2-GRC-S575 2MRC-c582 REACTOR COOLANT AZ 141 ELEv ~ 614'-10 1/8" RG PUNP No 2

REAcTCR CCCLANT Az 154 ELEV~ 610 5

STN GEN ~

No ~ 2 REAcTOR GCCLANT AX 317 ELEv 614'-10 1/8" RG PuNP No 4

REAOTCR GooLANT Az 331 ELEv 610'-5" STN, GEN ~ No REACTOR COOLANT AZ 223 ELEV~ 614'-10 1/8" RG PuNp No ~

REAOTOR CooLANT Az 208

~

ELEVe 610'-5" STgi GEN ~ No, 3 REAOTCR CooLANT Az 208 E Ev, 617'-II-7/8U STN GEN ~ No ~

YES NO NO Nn tIO NO Nn O

10 2-GRC-S592 REAOTCR CCCLANT. Az 282 ELEve 683'-3 1/8N IN PAE66URIzER ENCLOSURE NO

)IA

SAFFT RELATED HYDRAUL G SNUBBERSi C7 1 nn OO I

SNUBBER IIO 12 HANGER

~RI~Oe 2-GRC-S594 2-GRC-S596 2-GRC-S598 SYSTEM SNUBBER INSTALLED ON LOCATION AND ELEVATION REAOToR COOLANT Az 291 EI.Ev ~ 68>

> 9/16" I N PRESSURIZER ENCLOSURE REAOTOA GooLANT Az 292 ELKv 682'-11 1/8" IN PAKSSURIZKR EHCI.OSURK REAcT0R CooLANT Az 279 ELKv. 671 '-5 1/4" I H PRESSURIZER ENCLOSURE ACCESSIBLE OR HIGH RADIATION ESPEG IALLY D IFF IGUI TO REMVE ES 15 17 O..

18 O

cn GO It 2-GRC-S599 2-GRC-S609 2-GRG-$ 611 2-GRC-S62$

2-GRC-S624 RKAOTOA GooLAHT Az 289 ELKVe 672 4 1/2 IH PRESSURIZER ENCLOSURE REAOTQA 'cooLANT Az 28>

EI.Eve 689'>>.

5/16U I RESSURI ZER ENCLOSURE RKAcTCA CooLAHT Az 294 ELEv, 681'A 7/8H PAESSVR I ZER ENCLOSUAK RKAOTCA cooLANT Az 2'77 ELEv 682'-9 1/16" IH PAKSSURIZER ENCI.OSVRK REAGT0R CooLANT Az 247 ELKV~ 615IA ABOVE RELIEf TANK

, ~ ~

0 NO NO..

~3. 7-9 SAF RELA ED HYDRAULIC SNUBBERSi SNUBBER NO C)

O 19

~

Ao n) 20 21 22 24 HANGER

~RK~O 2-GRC-S626 2-GRC-5629

'-GRC-S6~

2-GRC-S6$ 2 2&RC-S6/1 2-GRC-S587 SYST&l SNUBBER.INSTALLED ON LOCATION AND ELEVATION RKACTCR CQCLANT Az 284 ELEve 692 ~

$/16 IN PRESSURIZKR ENCLOSURE REAGT0R CooLANT Az 28$

ELEVE 687~-4 1/16U IH PRESSURIZER ENCLOSURK REAOTCR CooLANT Az 291 ELKV. 672'-7'11/16" IN PRESSURIZER ENCLOSURE REACTCR CooLANT Az 291 EI.Ev 669'-$ 11/16" IN PRESSURIZER tNCLOSURE REAcTCR cooLANT Az 291 ELEv ~ 670'-11 11/16" IH PRESSUR I ZKR ENCLOSURE REAcTCR CooLAHT Az 260 ELEve 622I-4 1/4" ov RELIEs TANK ACCESSIBLE OR INACCESS IBLE ND'O NO

, ~

HIGH RAD IDION ESPEC IALLY D IFF ICUI ZONE RENOVE ED B

lD O

2g 26 2-FW-S1 2-FM-S2(L)

FEKou*TKR Az $14 ELEV. 6>4'-9U NEAR STtl ~

GEN. No.

1 FEEOMATER Az 26 ELEVE 63/'A" NEAR Sm.

GEN ~ No~

1 0

0 NO

~3. 7-9 SAFE Y RELATED HYDRAULIC SNUBBERSi SNUBBER NO n

O0 28 29 HANGER

~AK NOg 2-Fw-S2(u) 2-Fw-s3 r

2-FM-S4(L)

S/STEN SNUBBER INSTALLED ON LOCA ION AND ELEVAT ON FKKDMATK8 Az 26 ELKV~ 636~M NKAR SZHo GKN~ No ~

1 FccowATKR Az 20 ELKS 629'-9" NKAR SZNo GKN ~

No ~

1 FKKDMATKR Az 155 ELcv 637'-0" HKAR STHe GKN ~

No ~ 2 ACCESS IBLE OR INACCESS ISLE NO 0

NO 0

JO HIGH RAD IATION ESPEC IALLY 0 IFF I

BL-TO REMVE I cL I

I

~

~ ~

2-R4-S4(U) 2-FM-S6 2-Fw-s8(L}

2'-s8(u)

FKKDMATKR Az 155 ELcv. 641'-0" NKAR STho GKN ~ No ~ 2 f'KcowaTKR Az 163 ELKS 634 9

HKAR STg.

GKN~ No, 2 FccowaTcR Az 157 ELKS 629~-9N NKAR 8TH. GKNi No. 2 FKKDNATKR Az 204 ELcve 634'-9" NKAR

$ TH GKN ~ No+ 3 FccpwATKR Az 200 El eve 633'AN NKAR sTN.

GKN. No+ 3 Fccowizca Az 200 ELKV 636~-ON NKAR

Szv, GcN Noi 3 0

0 IO 0

HANGER

~RK~O>>

2-FW-S9 SNUBBER

'lO O0 I

Wort 2-FM-S10(L) 37 2-Fv-sio(u) 39 2-FM-S11 A

40 2-FW-S12 2wBD-s563(L)

R-a80-5/53(U) 41 43 2-GBD-S569(L) g 44 2-GBD-S569(U )

I 45..

2wBD-s568 TABLE 3.7-9 SAFET RELATED HYDRAULIC SNUBBERS+

I HIGH 'RAD IAT'ION ACCESS IBLE OR INACCESS ISLE SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION FKKowATER Az 194 ELKVe 629I 9 NEAR STtI. GEN. No. 3 0

~FEKowATER Az 334

,ELKV>> 634 W NEAR STtI ~

GKN ~ No ~ 4 0

.FEKowATER Az 334

.ELKV>> 636I-7N NKAR STII GEN

.No 4

0 FKEnwATER AZ 330 ELKV>> 634'-9" HEAR STtI ~

GEN ~ No ~ 4 FEEowATER Az 343 ELKV. 629'-9" NKAR STIIY GEN ~

No ~ 4.

iNO STIIY GEN ~ BLowoo'wH Az 275 ELKV~ 607I-11" IH ANNULUS 0

>TtI~

OEN ~ 8l ownoWN AZ 875~

ELEV>> 608tH IN ANNUI.US STII GEN>> BLowoowN Az 275 ELEVe 607'-11N JN ANNULUS STII>>

GEH BLownowH Az 275 ELEv 608'-6N IN ANNULUS STII~

GEN ~

BLO'WOOWH AZ 264 ELEV 608 I I

IH AttNULUS

~ e

'ESPEC IALL'Y D IFF ICU-

....!TO.: RB10VE...

INO 0:

INO INO NO NO NO

ABI.E 3. -9 SAFE Y R LAT 0 H ORAUL C SNUBBERS+

C)

OO I

StIUBBER

~tI~

49

- HANGER

+ARK~O>>

2-GRH-S6 2-GRH-S7 2-GRH-S24 2-GRH-S25

\\

SYSTEN SNUBBER INSTAllEO ON LOCATION AND ELEVAT ON RESIDUAL HEAT RECIOVAL ELrv>> 581'A" RHR Puttp RootI 2E RESIDUAL HEAT RgtIOVAL ELrv>> 581'-3" RHR PutIP Roon 2E RESIDUAL HKAT REIIOVAL ELEV>> 581IMH RHR Puttp RooN 2w RESIDUAL HEAT RgtIOVAL ELKv>> 580 A.

RHR Puttp ROOII 2W NO NO NO'CCESSIBLE OR HIGH RAOIATION ESPECIALLY OIFF)CUL1 INACCESS IBLE ZONE TO REMVE 5

54 55 2-GCCJ-S274 AC CW-S308 2-GCCW-S317 2-GCCW-S320 2-GGGW-S519

.2-GCCW-S52) 2-GGCW-S550 COMPONEtlT 'COOL IHO WATER EI.Kv>> 621'MH CCW Puttp AREA COHPONKNT COOL IHa WATER ELgv. 6'IO'-.. 1/2u GGW Puttp AREA'otIPONENT Cool IHO WATER ELgv, 621IWH CGW Puttp AREA

~

GOHPONfNT GOOLIHO WATER ELKv>> 610 tA GGW Puttp ARg*

GotiPONENT Cool INO WATER AZ 132" ElrV 623'-4u RC Puttp ARKA.

GOCIPDHENT GDQLIHO WATKR AZ 132 ELEV 624'-9H RC PutIP AREA GDHPDNEHT Cool IHO wATER Az 308 Et.gv>> 619I-3N RG Puwp AREA A

0

, ~

NO

S I

~

~

, IH 7

3.7-3 SAFETY RELATED HYDRAULIC SNUBBERSi SNUBBER NO 5759'ANGER HARK NO ecol-SS>8 2-GCCM-'S8$ 9 2m ccrc-s 840 SYSTEN SNUBBER INSTALLED ON LOCATION ANO ELEVATION COIIPONENT COOLINO MATER Eggy>> 621'0N CCW PutIP ARgA GotIPONENT COOL INO MATER EI.KV>> 621 0U CCM PUtIP AREA CotIPONENT COOL I NO MATER ELgv. 620'-0" CCW PUtIP.

AREA ACCESSIBLE OR INACCESS ISLE IIIGII RAD IATION ESPEG IALLY D IFF ICUL ZONE TO RB%VE WO NO NO 60 2-4CCM-S84$

3 GotIPONKNT COOL INO MATKR ELrv. 620'-5" GCM PutIP AREA NO NO

'61 62 2mccM-SN6 2-GGS-S6$ 4 GotIPONENT COOLINO MATER ELgy 596'-2 $/8N CGM PUtIP AREA CMEtlhVOL.coNTROI. Az 299 EL.gv, 61$ '-1U IN ANNULUB 0

IO Q

2-GCS-56/7 GNEtLEcVOL GoNTRQL Az 72 ELrv>> 608'-10" IN ANNULUO 64 65 2-GCS-5729 2-YiSS-1 GNENLVOL CONTRoL Az 2/4 ELKv>> 617'-0" RC PUtIP ARKA HAIN STtAII Az 8 ELEV>> 6$9i-1 1/4 BETMEEtl STII~

GEN ~ No>>

1 ANO 4 66 2HSS 2 HAIN BTEAtI Az 17 EL.rv. 6>5'-0U BKTuKKN STtI. GEN. No.

1 ANO 4 NO

/'ABLE 3.7-.I SAFETY RELA ED HYDRAULIC SNUBBERSi o

StIUBBER HANGER NO.

MARK NO A

~

o'7 2-HSS-$

SYSTEH SNUBBER INSTALLED ON LOCATION AND ELEVATION HAIN sTEAII Az 172 ELKV>> 6$9I-1. 1/4 BKTMEEH STII~

GEH>>

No>> 2 AHD ACCESSIBLE OR ii HIGH RADIATION ESPECIALLY DIFF ICU

s. INACCESS IBLE

~ ZONE TO RQ'10VE P

e,

~ 68 69 i 7P 71.

'4 I

C) 2~S-4 2-HSS-5 2-NSS-7 2-GS I-S47 2-QS I-S51 HAIN STEAN AZ 165 ELKV>> 6/5 M BETMEEN ST<I'LN~ No. 2 ANo >

HAIN sTEAN Az 191 ELEV>> 6>5 W BKTMEEH STIIY GEN ~ No>> 2 AND HAIN $TEAII Az 184 ELKV>> 6/9 1.1/4 BKTMEEN STIIY GEN ~ No ~ 2 AND $

HAIN sTEAII Az >494 ELEV 6/5 W BKTMKKN STN>>

GENT No>>

1 AND 4 HAIN STEAII Az f564 ELEV 639'-1 1/4" BETMEEH STN.

GKN No 1

ANo 4 SAFETY INJECTION SYSTEII ELcv>> 573'-0N SAFETY INJKOTIDN SYBTKII ELKv>> 573'-0N, O

0 NO NO NO YES ES O

75'-GSI-S575 SAFKTY IHJEOTIDH SYBTEII Az 65 ELcv. 598'-9 3/8" IH ANNULUB NO NO

~

~

/'ABIE 3.7-9 SAFETY RELATED HYDRAULIC SNUBBERSi StIUBBER KAtIGER ttO

~ttK tto~

76 2-GS I-S657 SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVAT ON SAFKTY INJKcTICN SYBTEII Az 185 ELEv 6'IO'-0" IN ANHuuus ACCESS IBLF OR INACCESS IBLE HIGH RADIATION ESPECIALLY DIFF ICUL'ONE TO REt%VE NO 77 78 2-GS I-S7O7 2-GCTS-S61 SAFETY INJEcT I CN SYsTEII Az 221 Et Kve 6OBI-7H NEAA RG PUHP Noes'ONTAINMENT SPRAY EI.EV 579~-3" CTS Pugp-AREA NO tin NO 79

'o 82 2-GCTWS113(E)

CONTAINMENT SPAAY ELKv 582 M'TS Putlp ARK*

ACTS-S113)ll)

CoNTAINQENT SpRAY EI.Eye '582'Wu CTS PuHP AREA ACTS-S11 l(N)

CONTAINHEHT SPR*Y El EV' 582 W INSIDE LKAK DETECTOR BOX PIPE CNASK ACTS-S114(S)

CONTAINMENT SPAA'Y ELEV~ 582'-0" IHS ICE LEAK OKTECTOR BOX I'IPK CHASE

"'A A

NO NO tIO NO NO O

83 ACTS-S115(N)

CONTh INQENT S pAA'Y ELEve 579'-6" INsloK LEAK OKTKCTOR BOX PIPE CHASK 2~CT~S115(S)

CONTA INHENT SPRAY ELEVe 579'-6" INSIOK LKAK DETECTOR BOX PIPE CHASE NO tin

SAFETY RELATED HYDRAULIC SNUBBERSi

~ '

OO 7CI C+

SNUBBER NO~

85 87 88 HANGER

~1'\\RK N~a 2-GCTS<<S116(E) 2-GCT-S116(M)

N/A N/A SYSTEN Sl'lUBBER INSTALLED

~ON LOGATION AtiO ELEVATION CotlYAINHENT SP RAY EI.KV 579'-6N INsloE LKAK OEYECTOR BOX PIPE CIIASK CONYAINHENT iPRAY ELEVE 57gt~

INSIOC LCAK OKTECTOR Sob PIPE CHASE STKAH GENERATOR NO ~

1 ELKv. 665>

STKAH GENKRATCR Noi 1

ELKV.

665'CCESS IDLE OR HIGH RAD IATION lNACGESS IBLE ZONE NO 0

ESPEC IALLY D IFF ICU TO RQ'AVE NO Nn ES ES 89 I

'90 91 92 N/A H/A N/A N/A N/A STEAH GENERATCR Noi 1

El.Eve 665t I

SYCAH GEIIERAYOR Noo 1

ELEV.

665'TCAH GENERATOR NO% 2 ELcv. 665t STCAH GEIICRATOR No ~ 2 ELEv. 665t STKAH GEtIERATOR No+ 2 ELEvo 665t Yl.S ES F.S O

94 95 N/A STEAH GEtIERAYOR NOy 2 ELcve 665!

STEAH GENCRAYOR No+ 3 EI.cv 665t ES ES

ABLE 3.7-9 SAF E

A EO

'AAUL C S UBBE S SNUBBER n

~lp O

96 I

Pl' 97 ro.

N/A N/A STKAH GENERAToR HO ~

Er.KV, 665r ~

STEAN GENKRAToR No+

EiEV. 665'.

IIANGER SVSTEH SNUBBER INSTALLEO

~4g~lp OllA lp A D ELEV 0

ACCESSIBLE OR AccEss 8

E

~

~

~

HIGH RADIATION 0

ESPECIALLY DlFFlmLT~

0 REflOVE ES

'98 l

99 100 I

1D1 1Q2 N/A N/A N/A N/A N/A S)TEAN GENKRAToA Hoo Er.EV. 665'.

STEAN GENERAToR No ~ 4 Er.EV. 665>.

STKAH GENKRATQR Hoo. 4 ELKvo 665

~

STEAN GENKRAToR No+

EiEV. 665>.

STEAH GKNERAToR No ~

Er.EV. 665'.

NO YES YES VES YES O

Snubbers may be ad ed to safety related systems without prior License Amendment to Table 3..7-9 provided that a revision to Table 3.7-9 is included with the next License Amendment request.

Modifications to the "High Radiation Zone" column due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table 3.7-9 is included with the next License Amendment request.

4

~

~

PLANT SYSTEMS 3/4.7.8 SEALED SOURCE CONTAIMINATION LIMITING CONDITION FOR OPERATION 3.7.8.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material, shall be free of > 0.005 microcuries of removable contamination.

APPLICABILITY: At all times.

ACTION:

a.

Each sealed sou'rce with removable contamination in excess of the above limits shall be immediately withdrawn from use and:

l.

Either decontaminated and repaired, or b.

2.

Disposed of in accordance with Commission Regulations.

The provisions of Specifigation 3.0.3 and 3.0.4 are not applicabl e.

SURVEILLANCE REQUIREMENTS 4.7.8.1.1 Test Requirements

- Each sealed source shall be tested.for leakage and/or contamination by:

a.

The licensee, or b.

Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

4.7.8.1.2 Test Frequencies

- Each category of sealed sources shall be tested at the frequency described below.

a.

Sources in use (excludin startuo sources and fission d'etectors reviousl sub'ected to core flux - At least once per six months for all sealed sources containing radioactive materials.

D.

C.

COOK - UNIT 2 3/4 7-34

d..Records of gaseous and liqui" radioactive material released to the environs.

e.

Records of transient of operational cycles for those Iacility components-identified in Table 5.7-1.

Records of reactor tests and experiments.

g.

Records of training and qualification for current members of the plant staff.

h.

Records of in-service inspections performed pursuant to these Technical Speci ficati ons.

Records of Quality Assurance. activities required by'the QA Manual.

j.

Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the PNSRC and the NSDRC.

T.

Records for Environmental Qualification which are covered under the provisions of oaraaranh

6. 13.

Records of the service lifes o8 hydraulic snubbers listed on Table 3.7-9 including the date at which service life commences and associated installation and maintenance records.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure."

6;12 HIGH RADIATION AREA 6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Mork Permit".

Any in'dividual or group of 'individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the pgdia-tion dose rate in.the area.

"Health Physzcs personnel shall be exempt from the RMP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radi ation areas.

D.

C.

COOK - VNIT 2 6-20 Amendment No.

53

PLANT-SYSTEMS 3 4.7.6 ESP VENTILATZON SYSTEM The OPERABZLZTY of the ESP ventilation system ensures that radio-active materials leaking from the ECCS equi.pment, within the pump room following a LOCA are filtered pzior to reaching the environment.

The operation of this system and the resultant effect on offsite dosage cal-culations was assumed in the accident analyses.

3/4 7.7 HYDRAULZC SNUBBERS All snubbers are required OPERABLE to ensure that the structural integri.ty of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.

Snubbexs excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure of failure of the system on which they are installed, would have no adverse effect on any safety-related system.

The visual inspection frequency i.s based upon maintaining a constant level of snubber protection to systems.

Therefore, the required inspection'nterval varies inversely with the observed snubber failures and i.s detexnd.ned by the number of inoperable snubbexs found during an inspection.

Znspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.

However', the zesults of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval.

Any inspection whose results required a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbezs ~- y ne gene-ically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable.

Generically susceptible snubbers are those which aze of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, ox'xe sind.laxly located or exposed to the same environmental conditions such as temperature, radiation, and vibrati.on.

When a snubber is found inoperable, an engineering evaluation is performed, in-addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversly affected by the inoperability of the snubber.

The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

D C.

COOK - UNZT 2 B 3/4 7-5 Amendment No'.

53

4 PLANT SYSTEM I

BASES To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals.

Observed failures of these sample snubbers shall require functional testing of additional units.

The service life of a snubber is evaluated via manufactured input and information through consideration of the snubber sexvice conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc...}.

The r~ement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.

These records willprovide statisti,cal bases for future consideration of snubber service life.

The requirements for the maintenance of records and the snubber service life review are not intended to affect plant opexation.

3/4.7. 8 SEALED SOURCE CONTAMQGLTXON The limitations on zemovable contamination for sources requiring leak testing, including alpha emittezs, is based on 10 CFR 70.39(c) limits for plutonium.

This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

3/4 7.9 PIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and" extinquish fires occuring in any portion of the facility where safety related equipment is located.

The fire suppression system consists nf the water system, spray and/or sprinklezs, CO2, Halon and fire hose stations.

The collec-tive capability of the fize suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fixe protection program.

In the event that portions of the fixe suppression systems axe inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.

D. C.

COOK UNIT 2 B 3/4 7-6 Amendment NO.

S3

B DES Zn &e event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the majoz fire suppression capability of the plant.

The requirement for a twenty-four hour repozt to the Commission provides for pzompt evalua-tion of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.

3/4 7.10 PENETRATZON PIRE BAKtXE5tS The functional integrity of the penetration fire barriers ensures that fires willbe confined or adequately retarded from spreading to adjacent portions of the facility.

This design feature mizdzd.zes the possibility of a single fixe rapidly involving several areas of the facilityprior to detection and ~guishment.

The penetration fixe barriers aze a passive element in the facility fire protection program and are subject to periodic inspections.

During periods of time when the baxriers are not functional, a con-tinuous fire watch is required to be maintained in the vicinity of the af ected barrier until the barrier is restored to functional status.

D C

COOK - UNZT 2 B 3/4 7-7 Amendment Ho.

53.