ML17333A215

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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 & Will Save Limited NRC Resources
ML17333A215
Person / Time
Site: Cook  American Electric Power icon.png
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. Indiana 'Michigan Power Co. (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 TITLE: SECY/DSB Dist: Public COPIES RECEIVED:LTR Comment on Proposed L Rule ENCL

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R) -Misc Notice; Reg G NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL INTERNA 'LEOGC/DR 15-B-18 R~ NMSS/IMOB RES DIR T8F5 RES/DRA/DEPY RES/DST EXTERNAL: NRC PDR NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2083 ) TO ELIMINATEYOUR NAME FROM

'ISTRIBUTION LISTS I'OR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 7 ENCL

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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 methodology work.

there is no waiting period after completion of the 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 AEP:NRC:1240 Page 2 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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