ML17326B581

Application for Amends to Licenses DPR-58 & DPR-74,revising Tech Specs for Diesel Generator Reliability

ML17326B581
Person / Time
Site:	Cook
Issue date:	04/06/1989
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Murley T NRC
Shared Package
ML17326B582	List: ML17326B581 ML17326B583
References
AEP:NRC:0896N, AEP:NRC:896N, NUDOCS 8904190020
Download: ML17326B581 (9)

Text

I:,,g ACCELERATED D BUT>ON DEMONS TlON SYSTEM REGULAT INFORMATION DISTRIBUTION STEM (RIDS)

ACCES)ION NBR:8904190020 DOC.DATE: 89/04/06 NOTARIZED: NO DOCKET

~ FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana a 05000315 50-,316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana 6 05000316 AUTH;NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana 6, Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. NRC No Detailed Affiliation Given

SUBJECT:

Application for amends to Licenses DPR-58 6 DPR-74,revising Tech Specs for diesel generator reliability.

I DISTRIBUTION CODE: ROOID TITLE: OR Submittal: General Distribution COPIES RECEIVED:LTR I ENCL J SIZE: S 4 V(n D

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 A STANGEJ 5 5 INTERNAL': NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 1 1 NRR/DEST/MTB 9H NRR/DOEA/TSB OC/LFMB ll 1 1

1 1

1 0

NRR/DEST/RSB 8E NUDOCS-ABSTRACT OGC/HDS1 1

1 1

1 1

0 8 LE 0 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 D

NVZE 'IO ALL "RIDS" RECIPIEÃIS'IZASE S

HELP US 'IQ REDUCE HASTE! CXWZACZ 'IHE DOCUMENT CGNZROL DESK RXN Pl-37 (EXT. 20079) K) EIaIMZNAXB %MR NME FBM DISTRIBUTION LISTS KHt DOHIMEMIS YOU DGNiT NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 20

Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:0896N Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 REVISED TECHNICAL SPECIFICATIONS FOR DIESEL GENERATOR RELIABILITY Attn: T. E. Murley April 6, 1989

Dear Dr. Murley:

This letter revises our application for amendment to the Technical Specifications (T/Ss) for the Donald C. Cook Nuclear Plant submitted in AEP:NRC:0896B dated January 16, 1987. A detailed description of the proposed revision is included in Attachment 1 to this letter. Attachment 2 contains a complete set of proposed revised T/S pages.

We believe the proposed changes will not result in (1) a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.

These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee.

In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr. R. C. Callen of the Michigan Public Service Commission and Mr. G Bruchmann of the Michigan Department of Public Health.

~

This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Sincerely, M. P. Al xich Vice President pool ldp Attachments n

SP00i90020 890+0>>

pDR ADOCK 0500 NU5 P

Dr. T. E. Murley AEP:NRC:0896N cc: D. H. Williams, Jr.

W. G. Smith, Jr. - Bridgman R. C. Callen G. CharnoEf A. B. Davis NRC Resident Inspector - Bridgman G. Bruchmann

ATTACHMENT 1 TO AEP:NRC:0896N REASONS AND 10 CFR 50.92 ANALYSIS FOR CHANGE TO THE DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS

Mi 1

to AEP:NRC:0896N Page 1 In AEP:NRC:0896B dated January 16, 1987, we submitted an application for amendment to the T/Ss for the Cook Nuclear Plant.

The proposed changes in that amendment were intended to improve diesel generator reliability. We revised that application in AEP:NRC:0896H dated November 25, 1987, and AEP:NRC:0896M dated March 23, 1989. AEP:NRC:0896B included a change to allow simulated load testing of our batteries. This proposed change was submitted separately in AEP:NRC:0896J dated April 29, 1988, and is being acted on by the NRC staff in a separate review.

The NRC staff has recently requested a number of revisions to our diesel generator T/S proposals. We have agreed to the requested revisions and this letter is intended to formally submit them.

Descri tion of Revisions The following revisions have been made to our diesel generator T/S proposals.

1) We have clarified Action b of Specification 3.8.1.1 by deleting the word "and" and adding the phrase "not to exceed." The phrase now states "...restore the diesel generators to OPERABLE status within 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, not to exceed an accumulated annual outage time of 576 hours0.00667 days <br />0.16 hours <br />9.523809e-4 weeks <br />2.19168e-4 months <br />..." rather than "...restore the diesel generators to OPERABLE status within 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> and an accumulated annual outage time of 576 hours0.00667 days <br />0.16 hours <br />9.523809e-4 weeks <br />2.19168e-4 months <br />...." This is an editorial revision for clarity.

2) We have modified Specification 4.8.1.1.2.a.5 to require loading the generator to 1750Kw rather than 1700Kw.

Anal sis of Si nificant Hazards The proposed T/S changes submitted in this letter are more restrictive than the proposed changes submitted in AEP:NRC:0896B.

The significant hazards analysis submitted in AEP:NRC:0896B remains applicable to the changes submitted in this letter and the proposed revisions are therefore covered by the existing Federal Register Notice. The revisions will not significantly increase the probability or consequences of an accident previously evaluated, create the possibility of a new or different accident from any accident previously evaluated, or significantly decrease a margin of safety and consequently do not constitute an unreviewed safety question as defined in 10 CFR 50.92.

ATTACHMENT 2 TO AEP:NRC:0896N REVISED PAGES FOR THE DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS

g't

~t f