ML20009H299

Amend 60 to License DPR-40,making Editorial & Administrative Corrections,Correcting Typographical Errors & Revising Organizational Charts

ML20009H299
Person / Time
Site:	Fort Calhoun
Issue date:	07/29/1981
From:	Clark R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20009H298	List: ML20009H297 ML20009H299 ML20009H300
References
NUDOCS 8108070198
Download: ML20009H299 (20)

Text

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f, UNITED STATES j h 5,( (,p, NUCLEAR REGULAFORY COMMISSION 5.p, M /a j WASHINGTON. D. C. 20555 e,, u

%;.N.r J, OMAHA PUBLIC POWER DISTRICT

' DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT 'l0.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 i

License No. DPR-40 h

1.

The Nuclear Regulatory Commission (the Com,nission) has found that:

l l

A.

The applications for amendment by the Omaha Public Power l

District (the licensee) dated March 13, 1978 and May 29, 1981, comply 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; i

B.

The facility will operate in conformity with the appli-cation, the provisions of the Act, and the rules and regulations of the Commission; I

l C.

There is reasonable assurance (i) that the activities l

authorized by this amendment can be conducted without i

endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i

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 j

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.

l 8108070198 8107E9 PDR ADOCK 05000285 P

PDR

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2.

Accordingly, Facility Operating License No. OPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and oaragraph 3.B. of Facility Operating License No. OPR-40 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications conta#ned in Appendices A and B, as revised through Amendment No.60, 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, k

FOR THE NUCLEAR REGULATORY C0Kr11SS10N 1

']

b ca Robert A. Clark, Chief Operating Reactors Branch =3 Division of Licensing

Attachment:

i Changes to the Technical Specifications Date of Issuance: July 29, 1981 0

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I ATTACHMENT TO LICENSE AMENOMENT NO. 60 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised l

pages are identified by amendment number.and contain vertical lines indicating the area of change.

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Remove Pages Insert Pages i

11 11 l

2-9 2-9 i

2-34 2-34 2-67 2-67 2-90 2-90 2-90a 2-94 2-94 2-95

?-95 3-3 3-3 3-20d 3-20d 4-3 4-3 Fig. 5-1 Fig. 5-1 Fig. 5-la l

Fig. 5-2 Fig. 5-2 5-5 5-5 5-6 5-6 I

5-7 5-7 5-8.

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O TABLE OF CONTENTS (Continued)

. Pare.

- c.=. F..tl-..C : o..r L. imp. CS.............................................. o -1 e..

3.,3 i o s. - - -

31 Instru=entatien and Centr:1....................................

3-1 3.2 Equipment and S a=pling Te st s...................................

3-17 3.3 Reacter C olant Systes, Steam Generacer Tubes, and Other Cc=penents Subject to ASME ZI Sciler L Fressure Vessel Code Inspecticn and Testing Surveillance.................... 3-21 3.h Reacter Coolant Syste ategrity Testing....................... 3-36 3-27 3.5 centain=ent Test................................................

3.6 Safety Injectica and Centain:ent Cocling Syste=s Tests......... 3-5h 3.7 I:ergency ?cuer Systes ?ericcic Tests.......................... 3-58 3.3 Main Stet: solatica Valves................................... 3 61 39 Auxiliary Feedva:er Syste=.................................... 3-62 3.10 Reacter Cere Para =eters........................................ 3-63 3.11 Enviren= ental Radi 1cgical Meniteri:s.......................... 3-6L 3.12 Radicactive Materials..........................................

3-69 3 13

.9adicactive Material Scurces Surve111a=ce......................

3 ~6 3.1k, Shock Suppresscrs (Snubbers)...................................

3-77 3.10 Fire Prctection Syste:.........................................

3 50

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h.2.2 Penetra:icas........................................... h _

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" n*. a.' -- -. 4.-.L. '.L.. uc'.'...-.-..=_s..................L--

w-k.3 Hucle ar Ste a= Supply Syste= ( USSS ).............................. h-3 www-..

... s. e-................................. --;

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d.3.3 3:ergency Cere OcCling............................

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.k Fuel Sterage.......................'............................ LL k.k.1 New Fuel Sterage.......

2--

Spent Fuel Sterage....................................., L k.k.2 a d

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2. v,

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ua...............................................

5.1 Respersibility.................................................

5-1 5.2 C. s an i c at ie n...................................................

5 -1 5.3 Facility Staf; qualifica:iccs.........................

5-ia 5.a Tr a in ir s.......................................................

5 - 3 55 Reviev end Audit 5-3 551 Plant Review Ccnsittee (?EC)..........................

5-3 5 5.2 Safe:y Audit p_ad Review Cc==ittee 'SARC)..............

5-3 5.5.3 Fire Protec:icn Inspectica............................

5-3 l

5.6 Reportable Occurrence Action...................................

5-5 s.O1. 4-.On.......................................... e o.

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.eace...

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4 3.3 E'.*cc edure s.....................................................

5-9 1

A:end:ent no. 33, #3, X6, 74, 60 11

.c.

r 2.0 LDIITING CONDITIONS FOR OPERATION l

2.1 Resetor Coolant Syste= (Continued)

' 2.1.3 Maxi =us Eeactor Coolant Radicactivity (Continued)

' tube rupture accident.(3) The potential dose at the site boundnr/

l for this accident is larger and hence = ore li=iting than the dese that vould result frem one year of operation with the t

l

axir.us reactor ecolans activity ec=bined vi-h the =axi=u

l per=issible unidentified leakage fre.,the reactor coolant syste=

l (Section 2.13 of these Specifications).

1 L

S e accidents for which pri=ary and secondary ecole =t concen-l trations becene the limiting pars =eters are a steam genera:cr tube rupture and a steam line break upstress of the isolatica valves, respectively, with the folleving tasic assu=ptions:

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(1)

Steas Generator Tube Rupture I

I

-a.

Maxi =u= per=issible tvo-heur doses a: the enclusien dista.nce of 1.5 re: o the thyroid, and 0.5 rer.whole body.

b.

Loss of offsite power.

c.

90,000 lbs. of pri=ar/ coolant is released to the secondarf.

d.

Identification of the ace

• " d pressure equali'-

catien between pri=ary a=1 secondary cccurs within 30

=inutes.

e.

Ten percent of the pr' * / coolant entering the secondarf syste= through the ruptured tube flashes and is released directly to the envirens, f.

~he quantity of stes= released frc= the secondary syste= is deter =ined frc= = ass and energy balances en the pri=a y and secondar/ syste=s, g.

Partitiening of iodine in the stes: released frc=

both stess generators by a fae:cr of 0.1.

(2)

Stea= Line 3reak I

l a.

Maxi =u= per=issible two-hour deses at the exclusion distance of 1 5 re= to the thyroid, and 0.5 res whole body.

b.

loss of offsite power.

c.

31cvdown of the centents of one steam generator.

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Amendment No. 60 2-9 l

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o 2.0 ' "..".. '."..G CC!.JI*. '.'CNS T. CR *v*. "~. A*.S.*7.

2.7 Ilectrical Syste=s (Centinued) l l

g.

One of the four a-c instru=ent buses :27 he incperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the reactor protective and enginee ed safe-l guards syste=s instru=ent channels supplInd by the re=aining three buses are all operable.

1 h.

Ovo battery chargers may be inoperible for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> pro-vided battery charger No.1 er No. 2 is cperable.

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i.

Iither ene of the diesel generators may be incperable fer up to seven days (total for bothl during any =cn:h, provided the l

cther diesel is started to verify cperability, shutdevn and l

centrols are left in the au c=stic =cde and there are no in-l operable engineered safeguards ec=penents associated with the operatie diesel generator.

j J.

1sland buses 132A LA,1332 k3, and 133C LC =ay be incperable

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=.~a. - c '..., e-* k ' e s a'a. g.a.-d.s cc penents asscelated with the cperable bus which are re-lu:.daat*to the incperable bus.

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Zither one of the DC buses (?anels II-87 and II-8G) =ay be incperable fer up to 3 hcurs.

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4 nay be ineperable for up to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

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a fica:icn is cade by telephene er telegraph to -he Directer cf the NEC 3egicnal Of fice in Arlington, Texas

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-.a 31 sis The electrical syste= equip =ent is arranged so that no single failure can inactivate enough engineered safeguards *o jeepardize the plant

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safety. The LSO V safeguards are arranged en nine bus sections. The h.16 kV safeguards are supplied frc= two buses.

The ner:al scur:e of auxiliary :.over vith the :lant at e.cver for the safeguards buses is frc= the hcuse service ;cver transformers being fed frc= the 161 kV incesing line with en-site e=ergency pcVer Anendnent No. 60 2,h c

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Instr 1.nent C*erating Requirerents fcr Reseter ??ctective Sys' tem

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Mini =u=

Mini =us Per=issitie i.

Operable Degree of 3ypass

- _d'tndanc:r Cendition Functional Unit Channels

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>:ssual (" rip 3uttens) 1 Ncne

Tene i

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2 Lgh' ?cver Level 2(bc)

'1(c)

Ther=al ?cver Input 3ypassed telev 10--",

of Rated ?cver(11 (i) 3elev 10 k' c' (i) 3 Ther=al Margin / lev 2(o) 1 Eated?cer(E)

Pressuricer Pressure L

High Pressuri er Pressure 2(b) 1

• !cne

e...,e 2.s 5

... R.a. :.cv 2(b) s...

3ated ?cver(1) (i) o

• cv Steam Generater 2/Syea=

1/Stes- '

!cne

'4a,er Level Gentb) gen 7

lov Stes: Generater 2/S*es:

1/Stes:

3elev 550 ; sis (S) (i)

GenbC)

Gen Pressure 3

Centainment High

'2(b)

uring les}. Tes

Pressure

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.,se.4,3

.e. (

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4 k

Zated ?cver '!

3elev 10--5 and abcve,e,

10 High Rate ! rip-Wide 2

1 155 cf rated pcVer(a,,

Eange ics Channels 11

• css of Icad 2(D) 1 3elev,1 % cf rated pcveriei a

3ypass su cestics117 re=oved.

b One Of the incperable channels sus-be in the tripped cenditica.

e' If two channels are incperable, lead shall be reduced to 70", er less Of rated pcVer.

d

?cr icv pcVer physics testing this trip may te bypassed up to 10-15 l

Of rated ;cver.

e Fer each cha.nel, the se=e bistable aute=aticsily activstes the icss of *. cad and Axial ?cver Distribution (A?D) trips and e.utent ically bypasses the high rate trip r.t 155 of rated pcVer. Only the AFD trip is a limiting Safety Systen Setting. Therefere, the bistable is se: Oc se:uate within the A?T) tolersace band.

l 4

Amendment No. 60

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O CA3LI 2-7 c 3. e.

s_.

c. - C.T cC w.._S

=one c

Ne.

Locatien 1

Auxiliary Building, Ilevatiens 9.71 and 969 West 2

Auxiliary Su11 ding, Ilevatien 989 Iast 3

.'.uxiliary Building, Ilevation 989, Lever Ilectrical Penetratica Recs (Recs 201 k

. Auxiliary Suilding, 21avatic= 989, Air Cc= presser Recs (Recs 191 5

Auxiliary suilding, Ilevatic: 1007, Ccrrider 26, ace:s 58, 59, and 60 6

Auxiliary 3uilding, Ilevatiens 1007 and 1011, Unecntrolled 7

Auxiliary 3uilding, Ilevation 1013, Upper Electrical Penetration 3ces (Rec 57) 3 Auxiliary Building, Ilevatiens 989 and 1007, 3eric Acid l

Tank Area, Dr"-'ng Area, New Fuel Area l

9 Auxiliary 3u11 ding, Ilevatfen 1036, Centrcl ace = Cc= plex, Centrol 3cc: Iallvays 10 Contain=ent, Ilevatica 1013, 3C Fu=p Cavities 11 Cc=tain=ent, Ilevation 99k l

12

• Contain=en:, Ilevatica 10L5 l

13 Auxiliary Euilding, Ilevatien ICES (Ece=s 69 and Til

,1L -

Turbine 3uilding, Ilevation 990 l

15 Ourbine 3u11 ding, Ilevation 1011 16 Ourbine 3uilding, Ilevatic: 1036 17 Centain=en: Fans VA-33 and VA-7D 13 Centainmen Fans 7A-3A and VA-TC 19 Ocn;ainment Fans 7A-2A and 7A-23 2C Centrol Rec = Fanels C3-1/2/3 3eturn Air 4

-..a.4

-....., C. a s.in.2a. an.a

.n 2w

.n 22 Centainten Purge Discharge Fans 7A-32A and 7A-323 23 OG-2 Roc = Ixhaust Fan, 7A-523 l

2h centain ent Purge Supply Fans 7A-2hA and 7A-2h3 I

25 cen:rci Rees and Ha11vay ventilatica cucts 26 Auxiliary Su11 ding (Centrolled) Supply Fans, VA-35.4 and 7A-353 27 Auxiliary 3uilding (Centrolled) Exhaus: Fans, 7A LCA, 7A LC3, and 7A h0C 29 Auxiliary Suilding (Uncentrolled) Supply Fans, 7A h5A and l

VA k53 l

29 Auxiliary Juilding (Uncentrolled) Exhaust Fan, 7A hi 30 Auxiliary Building Ilevator Zhaft Fan, VA-51 31 Centrol Recs Air Ccnditioning Fans, 7A k6A tnd VA k63 32 OG-1 Rees Exhaust Fan, VA-52A 33 Auxilisry Building, Ilevatien 1036 (3cc= 11) 3L Plant Sprinkler Flev 35 Auxiliary Building, CG-2 (Recs 6k) 36 Auxiliary Buildin6, OG-1 (Recs 63) 37 Intake Structure C, eluding Rav Water ?u=p Eces 33 Auxiliary Building Cpen Stairvell 39 Auxiliary 3uilding Open Hatchway A=end:en: No. 73, 60 2-90

F-l' l

TABLE 2-7

.(Continued) r-HALC t A.22.A FIRI 2C'ES l

2cne

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1 Cable Spreading Rocs j

2 Cable Spreading Recs 3

Centrol Roc = 'tal%-In Cabinets k

Control Rcem 'Jali-In Cabinets 5

Switchgear Roc =

~4est 6

S.ritchgear Recs

'4est 7

Switchgear Recm - East 8

Switchgear Roc = - East t

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A:nendment No. 60 I

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,_mie

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o TABIE. 2-8 J

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-FI3E HOSE STATICIT LOCATIO:fS i

So.

Loestion Elevation, Si::e

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1.

FP LIl Intake Structure 1012'-6" 1 5"/2.5" 2.

?? k?

Intako Structure 1012'-6" 1 5"/2.5" I

3

??-30 Yard Area At grade level 2 5" L.

F:-33 Yard Area At grade level 2 5" 5.-

??-3A Yard Area At grade level 2.5" 6.

??-3F Yard Area At 6:ade level 2.5" 7

??-37

*-d Area At grade level 2 5" 5.

??-30 fard Area At grade level 2 5

9

. FF-TA Auxiliary 3uilding 989'-0"

~i'.5"/2.5" t

10.

??-73 Auxilia / Building 969'-0" 1 5"/2.5" FF-70 Auxiliary 3uilding 989'-0" 1.5"/2.5"

- 12.

F? ~D Auxiliary 3uilding 989'-0" 1,5"/2.5" 42

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e:9,_v 4

en

_.-n/m.;-o

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1 14.

??-77 Auxiliar/ 3uilding 969'-0" 1.5"/2.5" 15

??-7",

Auxiliar/ 3cilding 969'-0" 1.5"/2.5" 16.

FF-5A Auxiliary 3uilding 10 n'-0"

. 5"/2 5" 17.

F?-63 Auxiliary 3uilding 1011'-0" 1.5"/2.5" 13.

F?-SC Auxiliary 3uilding 1011'-0" 1.5"/2.5" 19 FF-3D Auxiliary 3anding 1007'-6" 1 5"/2.5" 20.

??-8E Auxiliary Building ic07'-6' 1.5"/2.5" 21.

FP-SF Auxiliary Building 1007'.4" 1.5"/2.5" f

l 22.

FP-30 Auxiliary 3uil:iing ic07'-6" 1.5"/2.5" l

23.

FP-SE Auxiliary 3uilding IC07'-6" 1.5"/2.5" l

I Acendment ;io. 37, 71, 60 2-9h t

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FIRE HOSE STAIIC!i LOCATIO:iS Location Elevation Si::e 2.

??-9A Auxiliarf Building 1025'-0" 1.5"/2.5" 25.

??-93

~ Auxiliarf Building 1025'-0" 1.5"/2.5" 76.

FP-90

'kuillarf Suilding 1025'-0" 1.5"/2.5" 27.

FF-9D kuiliarf 3uilding 1025'-0" 1.5"/2.5" 28.

FP-10A kuiliarf 3uilding 1036'-0" 1 5"/2.5" 29

.??-103 railiarf Su11 ding 1036'-0" 1.5"/2.5" 30.

FF-10C Auxiliar/ Euilding 1036'-0" 1.5"/2.5" 31.

??-10D A=iliarf 3nilding 1006'-0" 1 3"/2 3" 32.

. TP-10E.

kailiarf Suilding 1036'-0"

~ '.5"/2 5" 1

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A=end:ent :To. 53, 60 -

2-95

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l TAlti.E 3-1 9ng HIHit-tilM FitiuttJKilClici FOlt CilFrK;1, CAI.11titATION;; ARID Tlctrilld OF litML"rOit PI(OTFCTIVE tiY:7rtM

+

nnn tiurveillance n

Chatuiel Descript.iott Finacti ota Freiluency Surveillance Method

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Power Ilange Safety a.

Check 11 a.

Comparison or four power o

Channels channel readings, for both neutron flux and thermal power.

b.

Adj uu ttaent.

D(I )

b.

Chunnel adjustment, to 8

agree with heat balance cal cul at. ion.

c.

Calibrate tII2)

Insternal test signal to c.

- and Test verify 1. rips, alarms, per-missives and a.1:ctioneer c i rcui t.s.

i

'I 2.

Wide-Hunge Logarithmic a.

Check u

a.

Coimpurison or four wide-range Neut.ron Mani t, ors readlangs.

b.

Tes t.( 3 )

P b.

Internal test signals to ves 11) tillH indicut. ion and trip, power level per ailusives, instrinnent. accurney.

3 Heuct.or Coolant. Flow a.

Check

i n.

Comparison or four separate LoLal riow ludicut. ions.

b.

Calibrate it b.

Known dirrerenLf al pressure applied to sensoru to culi-braLe al L loop elevices.

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c.

Test 11( 2 )

Illutable t. rip tester.I A) c.

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DESIGII-FEATURES k.3 Nuclear Stea= Su: ply System (Centinued) k.3.1 Reseter Coolant System (Continued)

The reacter ecolant system is designed and constructed in accordance with the AS'4E 3 oiler and Pressure Vessel Cede, Sectien III, Rules for Constructica of Nuclear Vessels including all addenda through the vin *er of 1967 and the Code for Pressure Piping USAS 331.1.

The reacter ecolant systen is designed for a pressure of 2500 l

sia and a te=r.erature of. 650c? exce-t for the t.ressuricer which i

ne.tclu=e of the reae:cr has a design te=perature of 700cy, j.

ecciant system is apprcxi=ately c,616 cubic feet.

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Render deter =inaticas in vriting with regard :c vhether-or not each ite= considered under 5 5 1.6(a) through (e) above ecnstitutes an unreviewed safety questien.

c.

Provide i=ediate vritten notification to the Sectica Manager - Cperations and the Safety Audit and Review Cec =ittee of disagree =ent between the Plant Review Cc=ittee and the Manager - Fort Calhoun Station; hcvever, the Manager - Fort Calhoun Statics shall have respcnsibilit/ for resolution of such disagree =ents pursuant Oc 5.1.1 above.

[eccids 5.5.1.8 Che ?le=t Review Cc=ittee shall =sintain written =inutes of each =eeting and ecpies shall be provided to the Sectic.1 Manager - C;erations and Chair an of the Safety Au **'

Review Cc=1 :ee.

5.'i.2. Safety Audit and ?.eview Cc= ittee (SAP.C's Function 5.5.2.~

The Safety Audit and Review Cc=ittee shall functica :c pre-vile the independent reviev and audit of designated activities in the areas of:

a.

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Chai= an: Divisien Manager - Inviren= ental and Regula:Ory a.r.oa.<

s Me=ber:

Assistant Gene **' vanager - Freducticn C;eraticns, Fuels, and IRA Me=ber:

Assistant General Manager - Electric Operatiens

.%_..4...-

a

-4....

Me.ber:

Divisien Manager - Ingineering Me=ber:

Divisien Manager - Freductien'0; era-icns Member:

CFPD Cperatiens, Engineering, and ""echnical Supper:

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u Required and as Deter =ir. ed by SARC Chai=an Anend=en No.,f, f.9, 60 5-5 T

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50 ADMII STP_CIVE C0rROLS

- Alternates

.5 5.2.3 Alternate =e=bers shall' be appointed in writing by the Chair-y i

=en of the Se.fety Audit and Review Cc==ittee to serve en a j

te=pora.'.y basis; hovaver, no =cre than *,vo a].ternates =ay participt.te in the Safety Audit and Review C~- 4ttee acti-vities at any ons ti=e.

j Censultants i

5 5.2.h Consultants shall te utiliced as dete.~ined by the Safety Audit s=d Review Cen=ittee Chair-e to provide exper advise to the Safety Audit and Review Cc==ittee.

Meetine Frecuency 5.5.2.5

'"he Safety Audit and Review Cc

• ttee shall =eet at least once every six =enths.

Querm 5.5.2.6 A quoru= of the Safety Audit and Review Cc-4ttee shall con-sist cf the Chair:an or his designated alternate and a =ajor-it/ of the Cafety Audit i". Review Cen=ittee =e=bers including alternates. He =cre than a =inority of the quer.=1 sW ' have -

line responsibility for the operation of the nuclear plant.

Reviev 5.5.2.7 he Safety Audit and Review Cc==ittee shall review:

a.

Se safety evaluatione for 1) proce'dures, equip =ent or syste=s and 2) tests or experi=ents cc=pleted under the provisien of sectic: 50.59, 10 G, to verify that such actions did not constitute an unreviewed safety ques;ien.

b.

? reposed changes to procedures, equip =ent or syste=s which involve a= unreviewed safety question as da'd-d sectica 50.59, 10 CFR.

i l-I l-l I

l k:end=en: No.., 19, 60 5-6 L

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l 5.5.27' c.

au.s <c. as d.a.#1.ed. '_7. sea.'. ~- 50."s9,

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Pre;csed changes in Technical Specifications or licenses.-

Violatiens of applicable statutes, codes, regulations, ceders, e.-

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• c a..s,.'.* c a__- s e -. c.ui. e~..~.'. s, *..' '..-.. e..al d.

y precedures or instructicas having nuclear safety sipi'icance.

f.

Si p ificant cperating abner:alities or deviaticus frca nc nal~

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Amendment No. 60 5_7

s m.4v_...e,.o.. IV ' CC..m..e.Cr S

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..m 5.O I

l 5.5.2.8 e.

The Fort Calhoun Station I=ergency Plan and i=ple=enting precedures at least once per two years.

f.

The Site Security Plan and imple=enting precedures at least ence l

per two years.

t I

g.

Any other area of facility operatica censidered appropriate by the j

Safety Audit - and' Review Cc==10:ee or the Assistant General Manager -

l Production Operations, Fuels, and Inviron= ental & Regulatory Affairs.

l Authcritr i

5.5 2.9 The Safety Audit and Review Cc==ittee shall report to and advise the Assistant General Manager - Productica Cperatiens, Fuels, and Invircn-l

= ental i Regulatory Affairs on those areas of respcasibility specified I

in Section 5.5.2 7 and 5.5.2.8.

ESCerds 5 5.2.10 Reccrds of Safety Audit and Eeviev Cc==ittee activities shall be pre-pared, approved. and dis ributed as indicated belev:

a.

Minutes of each Safety Audit and Review Cc d :ee =eeting snail be t.recared, at.:. roved and Cersarded to the Assis' ant General Manager - Freductica Operatic =s, Fuels, and Inviren= ental &

Regulatcry Affairs within ik days fciloving each =eeting.

l b.

Repc-- s of reviews enec= passed by Sectica 5.5.2.7 e, f, g, and h above, shall be prepared, approved and forwarded to the Assisten: Ceneral Manager - ?reductic: Operations, Fuels, and a'."a -. s

.-d..k...d.. - h c' a., s.'c _' '.- '....-

.4.-. _..., ;

2.. 7..3 3.,./.

d-Oc=ple:1cn of the reviev.

c.

Audi reports enec= passed by Section 5.5.2.3 abcve, sha be

.e

.ar'a.d..e.'a. a%. s ' s. a.. ".-e - e = = ' "- - a b..

. -. d".c '. '..', a -

s a icns, Fuels, and Inviren= ental & Regula: cry Affairs ani c the respensible --age =ent positiens designated by the Safety Aadi and Review Cc==ittee within 30 days after ce=pletien of

.u~ e,,. a.a...

5.5.3 Fire Frctecticn nsrection s.

An independent fire prctection and less preventica inspection and ="d'--- sk.=

k,e -..'c

.ad. ar.." a' ' g ".. d '

• 3..., e.4 '.e

,-ca' ' -

fled off-site licensee personnel or an outside fire protection f_r=.

The audit and inspection program responsibility shall rest with the Safety Audit and Review Cc==ittee.

b.

An inspection and audit of the fire protection and less pre-vention progrs= by an cutside qualified fire censultant shall be perfor=ed at intervals no greater than 3 years.

5.6 Fercr able Ceeurrence Actien 5.6.1 he folleving actions shall be taken in the event Of a R.CRCASLI r

o c..= =.=.- <n...

m a.

'.c Cc==issi i shall be notified and/or a repcrt sub=ine.i pursuant to the requirements of Specification 5.9 A=end=en: No. 9,19, 3"/, 60 5-8 g4-w w

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