ML25197A061
| ML25197A061 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/16/1975 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Anders W NRC/Chairman |
| References | |
| Download: ML25197A061 (1) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 Honorable William A. Anders Chairman U. S. Nuclear Regulatory Commission Washington, 0. C.
20555 July 16, 1975
Subject:
REPORT ON RANCHO SECO NUCLEAR GENERATING STATION, UNIT 1
Dear Mr. Anders:
During its 183rd meeting, July 10-12, 1975, the Advisory Committee on Reactor Safeguards reviewed the proposal of the Sacramento Municipal Utility District to increase the power level of the Rancho Seco Nuclear Generating Station, Unit 1, from 2568 MW(t) to 2772 MW(t).
This proposal was also considered at a Subcom-mittee meeting in Washington, D. C. on June 24, 1975.
In the course of its review, the Committee had the benefit of discussions with representatives and consultants of the Sacramento Municipal Utility District, the Babcock and Wilcox Company (B&W), and the NRC Staff, and of the documents listed.
The Committee last reported on the operation of this plant in its letter of September 11, 1973.
At that time, the Committee recom-mended that three conditions be satisfied before the plant was permitted to operate at its design power level of 2772 MW(t).
- a.
Operation of Unit 1 of the Oconee Nuclear Station, the prototype for Rancho Seco Unit 1, should be reviewed and found satisfactory by the Regulatory Staff.
- b.
Operation of Rancho Seco Unit 1 at 2568 MW(t) should be reviewed by the Regulatory Staff and the ACRS and determined to be satisfactory.
- c.
The Regulatory Staff should perform an independent confirmation of the licensee's linear heat generation rates, operating limits and ECCS efficacy, and should submit a supplemental Safety Evaluation Report.
These three conditions have been satisfied.
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Honorable William A. Anders July 16, 1975 The applicant is using control of the boron concentration in the core cooling water as an aid for reactivity control during power maneuvering.
During the past several months, plant operators have applied this system in a variety of power maneuvers.
Operating experience with the system to date has been acceptable.
The Advisory Committee on Reactor Safeguards believes that, if due regard is given to those items mentioned in its report of September 11, 1973, there is reasonable assurance that Rancho Seco Nuclear Generating Station, Unit 1, can be operated at design power (2772 MW(t)) without undue risk to the health and safety of the public.
References:
Sincerely yours,
/s/ W. Kerr W. Kerr Chairman
- 1.
Supplement No. 1 to the Safety Evaluation by the Directorate of Licensing, U. S. Atomic Energy Commission in the matter of Sacramento Municipal Utility District, Rancho Seco Nuclear Generating Station, Unit No. 1, Docket No. 50-312, Nov. 28, 1973.
- 2.
Supplement No. 2 to the Safety Evaluation by the Office of Nuclear Reactor Regulation, U. S. Nuclear.Regulatory Commission in the matter of Sacramento Minicipal Utility District, Rancho Seco Nuclear Generating Station Unit No. 1, Docket No. 50-312, June 10, 1975.
- 3.
Safety Evaluation Report by the Directorate of Licensing, U. S.
Atomic Energy Commission in the matter of Scramento Municipal Utility District, Rancho Seco Nuclear Generating Station Unit No. 1, Docket No. 50-312, December 27, 1974.
- 4.
Letter from E. K. Davis, General Manager, Sacramento Municipal Utility District of March 12, 1975 to Mr. Angelo Giambusso, Director, Division of Reactor Licensing, NRC, Re:
NRC Docket No. 50-312, Proposed Technical Specification Change No. 1, Rancho Seco Nuclear Generating Station, Unit No. 1.
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