ML20113C628
| ML20113C628 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/26/1996 |
| From: | Meisner M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO:-96-00075, GNRO:-96-75, NUDOCS 9607020018 | |
| Download: ML20113C628 (3) | |
Text
. _ _ _ _ _ _ _ _ _
A -
Ent:rgy cper:tixna,inc.
v ENTERGY no
- 7so Port Gt; son, MS 39150 Tel 601437 6470 M. J. Meisner Dr.acu b.:.K.kM' f.;aIsdy 8. %11Ltf08 / AfhDfS June 26,1996 U.S. Nuclear Regulatory Commission Mail Station P1-37 Washington, D.C. 20555 Attention:
Document Control Desk
Subject:
Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 Editorial Addition to Audit Change in GNRO-96/00042
References:
- 1) GNRO-95/00119 dated November 6,1995 from EOl to NRC
- 2) NRC letter dated January 3,1996 (Beckner to Hutchinson)
- 3) GNRO-96/00009 dated February 12,1996 from EOI to NRC
- 4) GNRO-96/00042 dated April 22,1996 from EOI to NRC GNRO:
96/00075 Gentlemen:
As requested by the Staff, we have made the additions to the Operational Quality Assurance Manual change we submitted. (Reference 4). These changes were i
discussed during telephone conversations on June 18,1996 and again on another telephone coversation on June 24,1996.
We appreciate the cooperation and attention of the Staff on this matter.
Yours truly,
/
d OculY m
MJM/mji attachment:
Proposed Grand Gulf Operational Quality Assurance Manual Changes cc:
(See Next Page) 9607020018 960626 PDR ADOCK 05000416 P
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- c-l GNRO-96/00075 Page 2 of 3 cc:
Ms. S. C. Black (w/a) (NRC/NRR)
Mr. A. Heymer(NEI)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
Mr. J. E. Tedrow (w/a)
Mr. H. L. Thomas (w/o)
Mr. J. W. Yelverton (w/a)
Mr. L. J. Callan (w/a)
Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 i
Arlington, TX '76011 Mr. T. P. Gwynn Director, Division of Reactor Safety U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 j
Mr. J. N. Donohew, Project Manager (w/2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555 Mr. A. C. Thadani Asociate DirectorforTechnical Assessment i
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555
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e t-to GNRO-96/00075 Page 1 of i j
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" Quality Assurance Program Requirements (Operation)" (Rev. 2, 2/78) - Endorses ANSI N18.7 - 1976.
The Operational Quality Assurance Program complies with the requirements of this Guide with the following clarifications:
1)
Paragraph C.3 of Regulatory Guide 1.33 (and Section 4.3.4 of ANSI N18.7 which it references) will be implemented as required by the applicable nuclear facility Technical Specifications which define
" Subjects Requiring Independent Review."
2)
Paragraph C.4
(" Audit Program") of Regulatory Guide 1.33 (and section 4.5 of ANSI N18.7 - 1976 which it references).
Audit frequencies will be implemented as required by the applicable Code of Federal Regulations, Updated Final Safety Analysis Report, and commitments by various correspondence to the NRC.
All other audit frequencies will be b ::d en performane ::: ult: and 4=pertence of th: ::tivity : lative t: :sfety determined in accordance with the performance-based audit scheduling program.
The scheduling program, through an expert panel, uses assessment indicators to identify and schedule audits based on performance results and importance of the activity relative to safety.
Potential audit subject areas are periodically assessed against appropriate performance criteria.
From these reviews a determination is made in regard to the depth, scope and scheduling of specific audits.
Functional areas important to safety are assessed annually (+25%) to identify strengths and weaknesses (if applicable) to determine the level and focus of independent oversight activities for the upcoming year.
The basis for the assessment shall include the results of QA audits and surveillance, NRC inspections, LERs (License Event Reports), self-assessments, and applicable condition reports (for example, nonconformance and corrective action reports).
Personnel changes, change / increase in functional area responsibilities, industry operating experience, and INPO evaluations may also be considered.
Each area will be assigned a rating with a comparison to previous years.
This assessment will be documented, reviewed and approved by QA Management. This document is considered a QA record and will be available for NRC review. Audit subject areas contained in Technical Specifications Section 6.5.2.8 prior to implementation of the Improved Technical Specifications in March, 1995 shall continue to be audited on the frequencies previously designated in the Technical Specifications unless expert panel judgment, based on performance results determines, such an audit to be unnecessary.
In such cases the expert panel basis shall be documented.
3)
Paragraph C.S.a of Regulatory Guide 1.33 (and Section 4.4 of ANSI N18.7 which it references) will be implemented with the clarification that the Plant Safety Review Committee shall perform this activity.