ML25196A427
| ML25196A427 | |
| Person / Time | |
|---|---|
| Issue date: | 09/15/1976 |
| From: | Moeller D Advisory Committee on Reactor Safeguards |
| To: | Rowden M NRC/Chairman |
| References | |
| Download: ML25196A427 (1) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 September 15, 1976 Honorable Marcus A. Rowden Chainnan U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
INTERIM REPORI' CN MONTAGUE PClvER STATION, UNITS 1 AND 2
Dear Mr. Rmiden:
At its 197th meeting, September 9-11, 1976, the Advisory Conmittee on Reactor Safeguards completed an interim review of the application of Northeast Nuclear Energy Company, acting as agent for a group of private and municipal utilities (Applicants), for permits to construct the pro-posed Montague Power Station, Units 1 and 2. This application was re-viewed at a Subcommittee meeting at Turners Falls, Massachusetts, on August 26-27, 1976, subsequent to a visit to the site on August 26. '!be Cormnittee also had the benefit of discussions with representatives and consultants of the Northeast Nuclear Energy Company, the Nuclear Regu-latory Commission (NRC) Staff, the General Electric Company, the Stone &
Webster Engineering Corporation, and of the documents listed. The Sub-canm.ittee also received statements from area residents.
The Montague Station will be located in Franklin County, Massachusetts, 1.2 miles south-southeast of the village of Turners Falls (1970 popula-tion: 5,168), and 3.5 miles east-southeast of Greenfield (1970 popula-tion: 14,642).
The minimum exclusion radius is 2,674 feet. The low population zone has a radius of 2.5 miles and a 1970 population of 4,476.
The nearest center of population is Northampton, Massachusetts.
The Montague Units 1 and 2 each utilize a General Electric boiling water reactor (BWR-6) 3579 MWt nuclear steam supply system (NSSS) and a Mark III type containment. The NSSS design is the same as that utilized for the GESSAR-238 Nuclear Island Standard Design. The Mark III type con-tainment design is similar to the Stone & Webster design utilized for the River Bend Station. The latest ACRS reports relative to nuclear generating stations utilizing the BWR-6/Mark III systems are the May 12, 1975 report on the Perry Nuclear Power Plant, the January 14, 1975 report on the River Bend Station, the May 13, 1976 report on the Hartsville Nuclear Plant, and the March 14, 1975 report on the GESSAR-238 Nuclear Island.
1012
Honorable Marcus September 15, 1976 The NRC Staff has completed a review related to the construction of the Montague Units based upon current information and current safety consid-erations. In view of a several year delay in the start of construction of these units, the NRC will require an update of this review, to com-mence approximately one year before the anticipated date for decision on issuance of construction permits. i'he ACRS will complete its review of this application at this time. All significant safety considerations identified in the interim will be included in the updated review.
i'he Mark III containment design has been under continuing review by the NRC Staff and the Committee. Results from tests made to date by the General Electric Company have led to criteria which are believed to be sufficiently conservative to allow for uncertainties in the currently applied empirical design methods. 'Ihe ACRS anticipates that the remain-ing tests of the program proposed by the General Electric Company will provide a basis for confirming the adequacy of the Mark III containment design for the Montague Station.
i'he Committee believes that the Applicants and the NRC Staff should further review t..~e Montague Units for design features that could significantly re-duce the possibility and consequences of sabotage, and that such features should be incorporated into the plant design where practicable.
Other generic problems relating to large water reactors are discussed in the Committee's report dated April 16, 1976. Those problems relevant to the Montague Station should be dealt with appropriately by the NRC Staff and the Applicants as solutions are found. 'Ihe relevant items are: II-1, 2, 4, 5, 6, 7, 8, 9, 10, 11; II-A-1, 2, 4, 6, 8; II-B-2, 3, 4; and II-C-1, 2,4,6,7.
The Advisory Committee on Reactor Safeguards believes that the above items can be resolved by the Applicants and the NRC Staff. Subject to the satis-factory resolution of these items and any new safety considerations that develop between now and the completion of the Committee's review of this application, the Committee believes that the Montague Power Station, Units 1 and 2, can be constructed with reasonable assurance that they can be operated without undue risk to the health and safety of the public.
1013 Sincerely yours,
~CV,t)J1~
Dade w. Moeller Chairman
Honorable Marcus September 15, 1976
References:
- 1.
Preliminary Safety Analysis Report (PSAR) for the Montague Nuclear Power Station, Units l and 2, Volumes 1-11 and Amendments 1-14
- 2.
Safety Evaluation Report, NUREG-0091, related to construction of ft:>ntague Nuclear Power Station, Units 1 and 2, July 1976
- 3.
General Electric BWR/6 Standard Safety Analysis Report, Volumes 1-9 and Question and Response Guide, Volumes 1 & 2 and Amendments 1-44
- 4.
Written statement received from Mr. George O'Brien, representing the International Brotherhood of Electrical workers Local Union #36, dated August 27, 1976
- 5.
written statement received from Ms. Elizabeth Bell, dated August 26, 1976
- 6.
written statement received from Mr. Robert May, dated August 11, 1976
- 7.
Written statement received from Ms. Joanne Katz, dated August 6, l.976
- 8.
written statement received from Ms. Juanita Nelson, dated August 26, 1976
- 9.
written statement received from Mr. Wallace F. Nelson, dated August 26, 1976
- 10. written statement received from Mr. Robert E. Murphy, dated August 26, 1976
- 11. written statement received from Mr. William Hefner, dated August 26, 1976
- 12. written statement received from 100 members of the public, dated August 25, 1976
- 13. written statement received from 27 members of the public, dated August 25, 1976 Revised Page 1014