ML16224A067

Proposed Resolution of Generic Issue 57, Effects of Fire Protection System Actuation on Safety-Related Equipment

ML16224A067
Person / Time
Issue date:	08/11/1993
From:	Wilkins J Advisory Committee on Reactor Safeguards
To:	Taylor J NRC/EDO
References
D930811
Download: ML16224A067 (2)

Text

D930811 Mr. James M. Taylor Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, D.C. 20555

SUBJECT:

PROPOSED RESOLUTION OF GENERIC ISSUE 57, "EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY-RELATED EQUIPMENT" During the 400th meeting of the Advisory Committee on Reactor Safeguards, August 5-6, 1993, we reviewed the proposed Resolution of Generic Issue 57, "Effects of Fire Protection System Actuation on Safety-Related Equipment." During this meeting, we had the benefit of discussions with representatives of both the NRC staff and its contractor, Sandia National Laboratories. Our Subcommittee on Auxiliary and Secondary Systems reviewed this matter during a meeting on July 28, 1993. We also had the benefit of the documents referenced.

We concur with the NRC staff proposal to resolve Generic Issue 57 by allowing risk-significant contributors to be dealt with by the Individual Plant Examination of External Events (IPEEE) program.

In view, however, of the importance of fire and fire-related problems, we would like to meet with the staff and review a few selected IPEEEs to see how well this process of generic issue resolution is working. We would like to be sure that important risk contributors like fire are receiving the special attention they need and that appropriate changes in the plants are resulting.

Sincerely, J. Ernest Wilkins, Jr.

Chairman

References:

1. SECY-93-143 dated May 21, 1993, for The Commissioners from James M. Taylor, Executive Director for Operations, NRC,

Subject:

NRC Staff Actions to Address the Recommendations in the Report on the Reassessment of the NRC Fire Protection Program

2. Sandia National Laboratories, NUREG/CR-5580, SAND90-1507, Vol.

1,

Subject:

Evaluation of Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment, December 1992

3. U.S. Nuclear Regulatory Commission, Draft NUREG-1472,

Subject:

Regulatory Analysis for the Resolution of Generic Issue 57:

Effects of Fire Protection System Actuation on Safety-Related

Equipment, with a memorandum dated May 5, 1993, from Warren Minners, RES, for John T. Larkins, ACRS