ML16274A147

Proposed Power Level Increase for Indian Point Nuclear Generating Station Unit 2

ML16274A147
Person / Time
Issue date:	02/15/1990
From:	Michelson C Advisory Committee on Reactor Safeguards
To:	Carr K Advisory Committee on Reactor Safeguards
References
D900215
Download: ML16274A147 (2)

Text

D900215 The Honorable Kenneth M. Carr Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555

SUBJECT:

PROPOSED POWER LEVEL INCREASE FOR INDIAN POINT NUCLEAR GENERATING STATION UNIT 2 During the 358th meeting of the Advisory Committee on Reactor Safeguards, February 8-10, 1990, we reviewed the application of Consolidated Edison Company of New York (Licensee) for a license amendment, to permit it to operate the Indian Point Nuclear Generating Station Unit 2 at a core thermal power level up to 3071.4 MWt. The current core power level limit is 2758 MWt, so this is approximately an 11 percent increase. This matter was discussed by our Subcommittee on the Systematic Assessment of Experience, on February 6, 1990. During these meetings, we had the benefit of discussions with representatives of both the NRC staff and the Licensee. We also had the benefit of the documents referenced. The NRC staff recommends approval of this application.

The plant was originally licensed in 1973, at a core thermal power level up to 2758 MWt, though the original analyses and supporting environmental assessments, with the exception of the emergency core cooling system (ECCS), were made for a core thermal power level of 3216 MWt. The ECCS was evaluated at 2758 MWt. There is nothing in the history to suggest that the lower power level of the original license was based on anything other than a (commendable) caution, since this was the first of the large Westinghouse 4-loop plants to seek a license. Since this is a license amendment, the staff review is based on the original license requirements, and our review is confined to the implications of the proposed power level increase, not to a review of the original license decision.

Since nearly all the original analyses were performed at the higher power, the remaining need was to demonstrate ECCS operability at the proposed power, and this was done in May of 1989. The analyses were reviewed by the NRC staff, and found to be in compliance with 10 CFR 50.46 and Appendix K, with suitable conservatism. We have no reason to question these conclusions.

Many new requirements, not all due to the Three Mile Island accident, have been levied since the original license was issued in 1973. Some of these are power related, and the staff should assure itself that those will be met at the new power level. The Licensee has assured the NRC, in a letter dated February 8, 1990, that that is the case.

Subject to resolution of this matter to the satisfaction of the NRC staff, we believe that the Indian Point Nuclear Generating Station Unit 2 can be operated at core power levels up to 3071.4 MWt

without undue risk to the health and safety of the public.

Sincerely, Carlyle Michelson Chairman

References:

1. Memorandum dated January 29, 1990 from S. A. Varga, Nuclear Regulatory Commission, to R. F. Fraley, ACRS,

Subject:

Transmittal of Revision to Draft Safety Evaluation to Increase Licensed Thermal Power Level of the Indian Point Nuclear Generating Unit No. 2

2. Letter dated September 30, 1988 from S. Bram, Consolidated Edison Company to U. S. Nuclear Regulatory Commission transmitting Application for Amendment to Operating License (Indian Point Station Unit 2)

3. Letter dated February 8, 1990 from S. Bram, Consolidated Edison Company to Donald S. Brinkman, Nuclear Regulatory Commission,

Subject:

Application for License Amendment to Increase Authorized Power Level