ML17319A632

Forwards Proposed Tech Spec Change for Section 3.1.1.4 Re Moderator Temp Coefficient.Plant Transient Reanalysis Results Reflecting Proposed Change Encl

ML17319A632
Person / Time
Site:	Cook
Issue date:	09/22/1980
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17319A634	List: ML17319A632 ML17319A635 ML17319A636
References
AEP:NRC:00453, AEP:NRC:453, NUDOCS 8010010539
Download: ML17319A632 (6)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8010010539 DOC ~ DATE: SO/09/22 NOTARIZED: NO DOCKET FACIL:50-316 Donald C. Cook, Nuclear Power Planti Unit 2i Indiana 8 05000316 AUTH. NAME AUTHOR AFF ILI.ATION HUNTERgR.ST Indiana 8 Michigan Electric IP. NAME RECIPIENT'FFILIATION Co.'EC DENTON~H.R. Office of,Nuclear Reactor Regulationi Director

SUBJECT:

Forwards proposed Tech Spec Change for Section 3 ~ 1 ~ 1 ~ 4 re moderator temo coefficient. Plant t ransient reanalysis results reflecting proposed change encl.

DISTRIBUTION CODE: A001S TITLE: General COPIESRECEIVED:L TR JENGL Distribution for after Issuance of I s1zE:

Opet 3w5c ating L'ic NOTES:Send copies of all material to I8E". 05000316 bv/C'her'8 3

4'li RECIPIENT doG'.

COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL-ACTION: VARGApS ~ 04 13 13 INTERNAL: D/DIRgHUM FAC08 1 1 I8E 06 2 2 NRC PDR 02 1 1 OELD 11 1 0 OR ASSESS BR 10 1 0 G I 01 1 1 EXTERNAL: ACRS 09 16 16 LPDR 03 1 1 NSIC 05 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR ~ ENCL

I I

I l

INDIANA L MICHIGAN ELECTRIC COMPANY P. 0. BOX 18 8OWLING GR E EN STATION NEW YORK, N. Y. 10004 September 22, 1980 AEP:NRC:00453 Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74

Subject:

Proposed Technical Specification Change

'oderator Temperature Coefficient Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, D. C. 20555

Dear Mr. Denton:

Attachment 1 to this letter contains a proposed Technical Specification change f'r, Unit 2 of the Donald C. Cook Nuclear Plant. We are requesting that the upper bound of the Moderator Temperature Coefficient given in Specification 3.1.1.4 be changed from OX10-4 hk/k/ F to +0 .5X10 " h k/k/ F for power levels below 70Ã Rated Thermal Power.

A plant transient reanalysis reflecting the proposed change was per-formed by Westinghouse Electric Corporation using the same methods employed for the FSAR analysis. The reanalysis results are presented in Attachment 2 to this letter. These data demonstrate that all criteria of the previous plant transient analysis are met and that the proposed change does not impact arly applicable safety limits . This TechnicaMpecification change has been',reviewed by both the PNSRC and the required membership of the AEPSC NSDRC in accordance with the provisions of our Technical Specifications.

These reviews concluded that the subject change will not adversely affect the health and safety of the public.

This Technical Specification change deals with a single safety issue which does not involve a significant hazard issue. Therefore, pursuant 170.22 of 10 CFR 170, a check in,the amount of $ 4,000.00 is also to'aragraph attached.

Very truly yours, R. S. Hunter Vice President cc: (attached)

~pp 0'pxppyp

v" V i A t

P I

\ ~

1 P'll ~ E

$)

WI i

Nr. Harold R. Denton, Director AEP:NRC:00453 cc: R. C. Callen G. Charnoff John E. Dolan R. W. Jurgensen D. V. Sha11er - Bridgman Resident NRC Region III Inspector - Bridgman

Attachment 1 to AEP;NRC:00453 Proposed Technical Specification Change