ML17319A830

Application to Amend License DPR-74 to Lower Axial Power Distribution Monitoring Sys turn-on Point from 94% Rated Thermal Power to 91%

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: ML17319A830 ML17319A832
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 AFF ILI ATION 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 COOK: A001S requested'ISTRIBUTION 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.

RECIPIENT COPIES RECIPIENT COPIES'TTR ID COOK/NAME LTTR ENCL IO COOK/NAME ENCL ACTION ~ 'ARGA c S ~ 04 13 13 INTERNAL; 0/DIR HUM FAC08 1 1 DIRcDIY OF LIC 1 1 ILE 06  ? 2 NRC PDR 02 1 1 OELD 11 1 0 BR 10 1 0 RAD ASMT BR 1 REG FILE 01 1 1 EXTERNAL: ACRS 09 16 16 LPDR 03 1 1-NSIC 05 1 1 At C.W~Y+.

g y$$,000.

~oxw'. 4 FOX.0O MAY 0 7 1981 TOTAL NUMBER OF COPIES REQUIRED: LTTR ~ ENCL

f" v

4 9 4

~

I f

II E

I 'I F

g f

J 9

Lr

INDIANA II MICHIGAN ELECTRIC COMPANY P. 0. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 May 1, 1981 g/

AEP:NRC:0564 dg leo Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 RE(VEST FOR UNIT 2 TECHNICAL SPECIFICATION CHANGES 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,

S. Hunter Vice President Enclosures cc

R. C. Callen G. Charnoff goo/

John E. Dolan - Columbus R. W. Jurgensen D. V. Shaller - Bridgman

~/i Region III Resident Inspector Bridgman ~/dec/g

~gg Ybao 00.

7>$ /.'g /ye O.OO 8~0~0~0

4

,I ~

4 l r' V s t "E '

)

l IK

~ ~

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 fuel supplier, Westinghouse Electric Corporation in their C

by the 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.