ML17331A781

Application for Amend to Licenses DPR-58 & DPR-74 Submitted as Revisions to Tech Specs Re Decay Heat Removal Capability & Refueling Cavity Water Level,In Response to NRC 800611 & 0815 Ltrs

ML17331A781
Person / Time
Site:	Cook
Issue date:	08/14/1981
From:	Maloney G INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17331A782	List: ML17331A781 ML17331A783
References
AEP:NRC:00420A, AEP:NRC:420A, NUDOCS 8108250255
Download: ML17331A781 (9)

Text

REGULA Y INFORMATION DISTRIBUTIO YSTEH (RIDS)

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SUBJECT:

Aopl i cat ion f zr aniend to Li censes DPR-58 F OP~ 7 suovitted as revisions to Tech-Soees re decay teat re>ova> caoaoility refuel<pa cav)ty water leveliin response to NR C 800eii 0815 I tr s.

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)NDIANA L MICHIGAN ELECTRIC COHPANY P. O. BOX 18 SOWLING GREEN STATION NEW YORK, N. Y. 10004 August 14 1981 AEP:NRC:0042OA Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 DECAY HEAT REMOYAL TECHNICAL SPECIFICATIONS Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulatory U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

This letter and its attachments provide our 'response to Mr. D. G.

Eisenhut's letter of June ll, 1980 submittal and Mr. T. M. Novak's letter of August of Technical Specification revisions 15, 1980 which requested concerning Decay Heat Removal Capability and Refueling Cavity Water Level, respectively.

Attachment 1 discusses the limited differences between the model Technical Specifications and those attached herein. Attachment '2'on-tains the proposed Technical Specifications for Unit 1 of the Cook Plant and Attachment '3'ontains the proposed Technical Specifications for Unit

2. These proposed Technical Specifications closely follow the guidance provided by the model Technical Specifications contained in the afore-mentioned NRC letters.

The proposed Technical Specifications contained herein have been reviewed by the Plant Nuclear Safety Review Committee and the American Electric Power Service Corporation Nuclear Safety 5 Design Review Committee.

As a result of these reviews, it has been concluded that implementation of the proposed Technical Specifications will not in any way endanger the health and safety of the general public.

gooi S

i/i Ln/ JC l~~l P 9goo.oo 8108250255 8i0814 PDR ADOCK 05000315 P PDR

Mr. Harold R. Denton AEP: NRC:00420A Indiana & Michigan Electric Company considers this submittal to be a Class III Amendment, with a 'duplicate unit'ee (Class I Amendment) added, as per the provisions of 10 CFR 170.22. Accordingly, attached is a check in the amount of $ 4,400.00.

Very truly yours, G. P. Malo y Vice Presi en cc: John E. Dolan, - Columbus G. Charnoff R. C. Callen R. W. Jurgensen D. V. Shaller - Bridgman Joe Williams, Jr.

Region III Resident Inspector at Cook Plant - Bridgman

Attachment No. 1 to AEP:NRC:00420A Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Decay Heat Removal Technical Specifications

'I ATTACHMENT 1 to AEP:NRC:0420A The Technical Specifications contained in Attachments '2'nd Units 1 and 2 of the Cook Plant respectively, reflect the requests

'3.'or of Mr. D. G. Eisenhut's letter of June ll, 1980 and Mr. T. M. Novak's letter of August 15, 1980. Mr. Eisenhut's letter requested submittal of Oecay Heat Removal Technical Specifications and Mr. Novak's letter addressed a Technical Specification on the Refueling Cavity >later level.

The attached specifications differ from the model specifications contained in Messrs. Eisenhut's and Novak's letters only in that:

(1) Under APPLICABILITY in Section 3.9.8.2 of both Units, an upper internals reference has been added. The water level indicated now refers.to limits when the upper internals are removed.

(2) The NRC model Surveillance Requirement in Section 4.9.8.1 of both Units has been replaced by the similar Specification already exist-ing which is suitable for this Surveillance Requirement.

(3) The Specifications under Surveillance Requirements in Sections 4.4.1.3.1 and 4.9.8.2 of Attachment 2 reference Specification 4.0.5. The latter does not exist as yet; however we plan': to sub-mit in the near future revisions to the Unit 1 Technical Specifi-cations which will include a Specification 4.0.5 very similar to the presently existing specification for Unit 2.

(4) Where the proposed technical specifications make reference to pressurizer or steam generator water volumes, the appropriate level has been given in percent of instrument span.

Attachment No. 2 to AEP:NRC:00420A Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Decay Keat Removal Technical Specifications