ML17333A215
| ML17333A215 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/11/1995 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| FRN-60FR54712 60FR54712-00009, 60FR54712-9, GL-83-11, NUDOCS 9512140224 | |
| Download: ML17333A215 (4) | |
Text
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REGULATOR< 'INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9512140224 DOC.DATE: 95/12/11 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
050003l5 50-316 Donald C.
Cook Nuclear PoAer Plant, Unit 2, Indiana M
05000316 AUTH.NAME
. AUTHOR AFFILIATION FITZPATRICK,E.
(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Division o2 Freedom of Information 6 Publications Services
SUBJECT:
Comment supporting draft GL 83-11,Suppl 1 providing guidelines to licensees who wish to perform their own safety reactor core design analyses. Eliminates need to submit detailed topical reports 6 will save limited NRC resources.
DISTRIBUTION CODE:
DS09D COPIES RECEIVED:LTR L ENCL SIZE:
TITLE: SECY/DSB Dist: Public Comment on Proposed Rule
(
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NOTES:
RECIPIENT ID CODE/NAME INTERNA 'LE
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OGC/DR 15-B-18 RES/DRA/DEPY EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME NMSS/IMOB T8F5 RES DIR RES/DST COPIES LTTR ENCL NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACTTHE DOCUMENTCONTROL DESK, ROOM Pl-37 (EXT. 504-2083 ) TO ELIMINATEYOUR NAME FROM
'ISTRIBUTIONLISTS I'OR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
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Power Company PO Box 16631 l'Calfà Columbus, OH 43216 I'3
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INOIANA NlCHEGAN PQWM December 11, 1995 AFP:NRC:1240 Docket: Nos.:
50-315 50-316 Chief, Rules Review & Directives Branch U. S. Nuclear Regulatory Commission Mail Stop T-6D-69 Washington, DC 20555-0001 Gentlemen:
Donald C.
Cook Nuclear Plant Units 1 and 2
COMMENTS ON DRAFT GENERIC LETTER 83-11, SUPPLEMENT 1
(LICENSEE QUALIFICATION FOR PERFORMING SAFETY ANALYSES)
In the October 25,
- 1995, Federal Register Notice (60 FRN 54712),
the NRC promulgated a draft set of revised guidelines to licensees who wish to perform their own safety and reactor core design analyses.
This set of guidelines would replace those in Generic Letter (GL) 83-11, issued February 8,
1983.
The purpose of this letter is to provide comments regarding the draft guidelines.
We concur with the NRC's decision to shorten the reeiew and approval process by eliminating the need to submit detailed topical reports.
We believe the guidelines provided in At:tachment 1 to the generic letter supplement will continue to assure that the design analysis is performed using a valid methodology.
Also, the new approach will save limited NRC resources currently required for methodology review and result in more eficient use of utility resources if there is no waiting period after completion of the methodology work.
As a recommended clarification on one of the points given in the generic letter supplement, the following comment is provided.
9512140224 951211 PDR ADOCK 05000315 PDR
U.
S. Nuclear Regulatory Commission Page 2
AEP:NRC:1240 Comment Attachment 1 to the draft generic letter supplement provides guidelines for licensees to use approved codes.
Section 2.1 in Attachment 1 states:
"The only codes and methods that are addressed by this process are those that the NRC has reviewed and approved."
Different versions of previously approved codes (e.g.,
core design codes) that have been modified by the vendor to correct errors or to incorporate enhancements to the codes should be acceptable.
It is suggested
- that, as long as the calculational methodology is not
- changed, the licensee should be able to use the new version of the code.
Sincerely, E.
E. Fitzpatrick Vice President eh CC',
A. Blind G. Charnoff H. J. Hiller NFEM Section Chief NRC Resident Inspector
- Bridgman J.
R. Padgett T. E. Tipton - NEI
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