ML17319A830
| ML17319A830 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/01/1981 |
| From: | Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17319A831 | List: |
| References | |
| AEP:NRC:0564, AEP:NRC:564, NUDOCS 8105070173 | |
| Download: ML17319A830 (5) | |
Text
1 i'g,'EGULATOR~NFORMATION DISTRIBUTION TEM (RIOS)
ACCESSION NBR:8105070173 DOC ~ OATEN'1/05/01 NOTARIZED'O DOCKET' FACIL:50 316 Donald C.
Cook Nuclear Power Planti Unit 2c Indiana I 05000316 AUTH,NAME AUTHOR AFFILIATION HUNTERcR ~ ST Indiana L Michigan Electric Co, RECIP ~ NAME'ECIPIENT AFFILIATION DENTONcH ~ RE Office, of Nuclear Reactor Regulationc Director SIIJIBJICT: Forwards proposed Tech Spec changes to lower axial power distribution monitoring sys turn on point from 94K rated-thermal power to 91K ~ Review requested'ISTRIBUTION COOK:
A001S COPIES RECEIVED:LTR ~NCL SIZP p+~
TITLE'. General Distribution for af ter Issuance of Operating License
'NOTES:Send 3 copies of all material to IItE.
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INDIANA II MICHIGAN ELECTRIC COMPANY P. 0.
BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 May 1, 1981 AEP:NRC:0564 Donald C.
Cook Nuclear Plant Unit No.
2 Docket No. 50-316 License No.
DPR-74 RE(VEST FOR UNIT 2 TECHNICAL SPECIFICATION CHANGES g/
dg leo Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Denton:
Attachments 1
and 2 to this letter contain proposed Technical Specification changes.
These changes have been reviewed by our Nuclear Safety and Licensing Section in its advisory role to the NSDRC and by the Plant Nuclear Safety Review Committee.
These reviews indicate that the subject changes will not adversely affect the health and safety of the public.
The matter will receive the review of the AEPSC NSDRC at its next meeting.
Your urgent attention to this matter is kindly requested.
Each Technical Specification change deals with a single safety issue which does not i'nvolve a significant hazard issue.
Therefore, pursuant to paragraph 170.22 of 10 CFR 170 two checks in the amount of
$4,000.00 are also enclosed.
V y
ruly yo s,
Enclosures S. Hunter Vice President cc:
R.
C. Callen G. Charnoff John E. Dolan - Columbus R.
W. Jurgensen D. V. Shaller - Bridgman Region III Resident Inspector Bridgman 8~0~0~0 goo/
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Attachment No.
1 to AEP:NRC:0564 The changes included in this Attachment in effect lower the Axial Power Distribution Monitoring System (APDMS) turn on point from 94% Rated Thermal Power (RTP) to 914 RTP.
The Axial Flux Difference (AFD) curve and specifications are also changed to reflect this.
These changes are a result of the slightly different core power profile associated with the Cycle 3 design.
The new values were recommended C
by the fuel supplier, Westinghouse Electric Corporation in their reload safety evaluation.
The proposed changes are indicated by a vertical line in the right margin.
Reload Safety Evaluation, D.
C.
Cook Nuclear Plant, Unit 2, Cycle 3, Westinghouse Electric Corporation, December 1980.