ML17321A653
| ML17321A653 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/21/1985 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17321A652 | List: |
| References | |
| AEP:NRC:0916A, AEP:NRC:916A, NUDOCS 8506070329 | |
| Download: ML17321A653 (3) | |
Text
INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 Nay 21, 1985 AEP:NRC:0916A Donald C.
Cook Nuclear Plant Unit No.
2 Docket Ho. 50-316 License Ho.
DPR-74 Unit 2, Cycle 6 Safety Analyses th. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Hashington, D.
C.
20555
Dear tfr. Denton:
The schedule for completing the Unit 2, Cycle 6 safety analysis was established in a meeting with the NRC staff on December 13, 1984 based on a December 1985 startup date.
As per this schedule, the first set of the analyses is to be transmitted to the NRC for review in July
- 1985, and the second set in August 1985.
Since the revised startup date for Cycle 6 is now January
- 1986, we propose to submit the safety analyses documentation in accordance with the following schedule:
1)
LOCA analysis and part of the Plant Transient analyses
- August 1985 2)
Remaining Plant Transient analyses with the exception of the Steamline Break Accident September 1985 3)
Steam Line Break Analysis (SLBA)
- July 1986 As discussed in the meeting, the steamline break accident for Cycle 6
will be performed using the Exxon Nuclear RELAP5 based methodology.
Until such reanalysis of the SLBA is completed by mid-Cycle 6, we believe that continued operation of the plant is justified on the same basis as it was allowed for Cycle 5.
The reason for this is that at least through the major portion of Cycle 6, the key parameters associated with the SLBA will be within the bounds of those same parameters allowed for Cycle 5
operation.
As we discussed with your staff, we would like to meet with the NRC staff on Hay 30, 1985 to discuss the current status of Exxon safety analyses.
This will include both transients and ECCS/LOCA methodologies and applicat-'ons.
850607032'P 850531 PDR ADOCK 050003l6 P
Mr. Harold R.
Den AEP:NRC:0916A This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accur acy and completeness prior to signature by the undersigned.
Very truly yours, Vice President
>'j'
~
GJ/b js Attachment cc: John E. Dolan W.
G. Smith, Jr. - Bridgman R.
C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman
~ ~
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