ML16204A245
| ML16204A245 | |
| Person / Time | |
|---|---|
| Issue date: | 08/15/1996 |
| From: | Kress T Advisory Committee on Reactor Safeguards |
| To: | Shirley Ann Jackson NRC/Chairman |
| References | |
| Download: ML16204A245 (2) | |
Text
August 15, 1996 The Honorable Shirley Ann Jackson Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Dear Chairman Jackson:
SUBJECT:
DESIGN CHANGES PROPOSED BY GENERAL ELECTRIC NUCLEAR ENERGY RELATING TO THE CERTIFICATION OF THE U.S. ADVANCED BOILING WATER REACTOR DESIGN During the 433rd meeting of the Advisory Committee on Reactor Safeguards, August 8-10, 1996, we reviewed recent design changes proposed by General Electric Nuclear Energy (GENE) relating to the certification of the U.S. advanced boiling-water reactor (ABWR) design. These "design changes" consist of both actual modifications to the design and corrections to the documentation to remove inconsistencies and typographical errors. We had the benefit of discussions with representatives of the NRC staff and of GENE. We also had the benefit of the documents referenced.
Conclusions Our review of Supplement 1 to NUREG-1503, "Final Safety Evaluation Report Related to the Certification of the U.S. ABWR Design," did not change the conclusion reached in our earlier report of April 14, 1994. We continue to believe that acceptable bases and requirements have been established in the application to assure that the U.S. ABWR Standard Design can be used to engineer and construct plants that with reasonable assurance can be operated without undue risk to the health and safety of the public.
Background and Discussion We have been involved in the review of the U.S. ABWR design since GENE applied for certification. This review was carried out in accordance with 10 CFR Part 52, which requires ACRS to report on those portions of 10 CFR Part 52 applications that concern safety. In our April 14, 1994 report to the Commission, we supported the certification of the U.S. ABWR design. This report was included in the staff Safety Evaluation Report (NUREG-1503). The present review is intended to supplement our earlier review of this ABWR application.
Sincerely,
/s/
T. S. Kress Chairman
References:
- 1. U. S. Nuclear Regulatory Commission, NUREG-1503, Supplement No. 1, "Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design," dated July 1, 1996
- 2. Staff Requirements Memorandum dated June 11, 1996, from John C. Hoyle, Secretary, to John T. Larkins, ACRS, regarding meeting with Advisory Committee on Reactor Safeguards, May 24, 1996
- 3. ACRS Report dated April 14, 1994, from T. S. Kress, Chairman, ACRS, to Ivan Selin, Chairman, NRC,
Subject:
Report on the Safety Aspects of the General Electric Nuclear Energy Application for Certification of the Advanced Boiling Water Reactor Design
- 4. Letter dated April 16, 1996, from J. F. Quirk, GE Nuclear Energy, to Dennis M. Crutchfield, Nuclear Regulatory Commission, regarding ABWR design changes
- 5. Letter dated July 1, 1996, from J. F. Quirk, GE Nuclear Energy, to the Nuclear Regulatory Commission,
Subject:
ABWR Design Control Document Changes