ML20032E248

Forwards Corrected Pages 137g & 153 of Amend 74 to License DPR-46 Transmitted in

ML20032E248
Person / Time
Site:	Cooper
Issue date:	10/29/1981
From:	Siegel B Office of Nuclear Reactor Regulation
To:	Pilant J NEBRASKA PUBLIC POWER DISTRICT
References
NUDOCS 8111200069
Download: ML20032E248 (4)

Text

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OCT p p 199, Docket No. 50-298 e-

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Mr. J. H. Pilant, Director Licensing & Quality Assurance NOVO 31981* $

Nebraska Public Power District p ->

P.O. Box 499

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Dear Mr. Pflant:

By letter dated October 7,1981 we transmitted Amendment No. 74 to Facility Operating License No. DPR-46 for the Cooper Nuclear Station.

It has been brought to our attention that page 1379 omitted the word

" Area" in the last line of that page. Also page 153a contained informa-tion which duplicated information on page 153. Page 153 was not included with the amendment.

Please insert the enclosed pages 137g and 153 in your copy of the Technical Specifications. We hope this has not caused any inconvenience.

Sincerely, ORIGIIIAL SIGNED BK i

Byron L. Siegel, Project Manager Operating Reactors Branch f2 Division of Licensing i

Enclosure:

Distribution:

Pages 137g & 153 z,06cket File i

NRC PDR cc: w/ enclosure Local PDR See next page ORB #2 Reading D. Eisenhut B. Siegel S. Norris i

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Mr. J. M. Pilant Nebraska Public Power District' cc:

Mr. G. D. Watson, General Counsel

-Nebraska Public Power District P. O. Box 499 Columbus, Nebraska 68501 Mr. Arthur C.; Gehr Attorney Sr. ell & Wilmer 3100 Valley Center Phoenix, Arizona 85073 Cooper / Nuclear Station ATTN:

Mr. L. Lessor Station Superintendent P. O. Box 98 Brownville, Nebraska 68321 Auburn Public Library 118 - 15th Street Auburn, Nebraska 68305 Director Nebraska Dept. of Environmental Control P. O. Box 9'577, State House Station Lir.::ir., Nebraska EE509 Mr. William Siebert, Co= issioner Ne tha County Board of Commissioners Neraha County-Courthouse Aubu n, Nebraska 6?305 Mr. Dennis Dubois

. U 3 ' =. C Resident. Inspector P. O. Box 218 -

Brownville, NE 68321 s

U:. 5. Environmental Protection Agency Region VII Office Regicnal Radiation Peprisentative 324 East lith Street Kansas City, MO. 64106 e

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S AFF.T.' RELATD EYDRAULIC SNLC" SUPPROSSORS (S.iUSSihS) (Cont'c)

Snuboer No.

Location Eleva:1on MS-5-17 "A" R11R Ex Rs 904' MS-S-18 "A"

R11F, h am 905' HS-5-19 "A" klLR Ex Rm

.923' etS-S-20 "A" RER Mx Rm 934' MS-S-20A "A" 8.:.'R Ex hs 934' y.5-S-23 Torus Area 896' MS-5-24 Torus area d98' MS-5-25 N.E. Quac 877' 35-5-26 N.E. Quac e79' Ms-S-75 "A" R1LR ax R=

9J2' ris-S-7 0 "B".tiR h Rs 932' I

c15-S-111A "A" hiiR dx Rs 923' RCC-S-3 Rx 31dg, 931' 945' RCC-S-*

Rx Bldg 931' 943' l

RCC-5-20 dx 31cg, 931' 953' l

RCC-5-21 Rx Bldg 931'

~ 95 3'

~

RCC-5-22 Rx Sidg, 931' 953' i

RF-5-1 N.E. Quac

~698' kF-S-1A N.E. Quac d96' RF-S-2

i. E. To rus Area 896' RF-S-3

1?CI R=

870' RF-5-*

S.U. Torus Area 894' xy-5-5 S.0. Torus Area 8'97' I

RF-S-6 S.'.J. To rus Ar e a 891' RF-S-*5C N.d. Quac 882' RF-S-45D N.E. Quac 882' RF-S-46A N.E. Quad 882' RF-S-51A li. E. Torus 397' i

RF-S-513 N.E. To rus 397' Rii-5-20 Rx Sids, 903' 912' RH-S-21 Rx 31d;;, 903' 9'l' Rd-S-22 Tcrus Area 690' R2-S-23 Torus Area 892' d97' Rd-S-24 Torus Area RH-S-25

.l.~REF. Ex Rs 927' Ku-S-25A Rx Bldg. 903' 922' RH-S-26 N. RFR ax R=

929' R11-5-27 A fLik Ex Rs 933' r

RH-S-29 b 5 a g, 903' 904' d93' RH-S-30A 2 us trea Ru-S-30E

,ia Area d9d' 694' Rn-S-32

. n. Area d92' Ril-S-3 3D Iorus Mea Amendment No. 74

-137 -

5

5.6.G & 4.6.G BASES (cont'd).

f.:.tegory J (1)

The more frequent inspections delineated for the Category J (1) pipe welds are to provide additional conservatis:n in the overall approach of protection against pipe whip which has the potential to breach the con-tainment. A pipe whip. protection system has been installed consisting of crushable panels located such that the postulated pipe weld failure will not breach the containment. Additional inspection of critical welds is also included in the inse vice inspection program. The J (1) welds listed on Table 4.6.4, are those pipe welds of interest.

An ~ ~ 3 = tion of the vessel clos = e head internal se face will be made at the end of the first ten year period. The rate of cor osion will be evaluated and compared tu :he design ec..esion rate. The results of this study will be used to forr11 ate the requirenents for fut=e testing.

Additional info =ation on the CNS Inservice Inspection Progra= is presentled in the FSAR Appendix J.-

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Amendment No. E 74 153

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