ML17319A632
| 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: |
| References | |
| AEP:NRC:00453, AEP:NRC:453, NUDOCS 8010010539 | |
| Download: ML17319A632 (6) | |
Text
SUBJECT:
Forwards proposed Tech Spec Change moderator temo coefficient. Plant t
results reflecting proposed change for Section 3 ~ 1 ~ 1 ~ 4 re ransient reanalysis encl.
TR JENGL I s1zE: 3w5c after Issuance of Opet ating L'ic 05000316 DISTRIBUTION CODE:
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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 Co.'EC IP. NAME RECIPIENT'FFILIATION DENTON~H.R.
Office of,Nuclear Reactor Regulationi Director INTERNAL: D/DIRgHUM FAC08 NRC PDR 02 OR ASSESS BR 10 1
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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 to'aragraph 170.22 of 10 CFR 170, a check in,the amount of $4,000.00 is also attached.
Very truly yours, cc:
(attached)
R.
S. Hunter Vice President 0'pxppyp
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Nr. Harold R. Denton, Director AEP:NRC:00453 cc:
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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