ML19323B105
| ML19323B105 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 04/14/1980 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| Shared Package | |
| ML19323B103 | List: |
| References | |
| NUDOCS 8005090264 | |
| Download: ML19323B105 (3) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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Sacramento Municipal Utility
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Docket No. 50-312 District
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(Rancho Seco Nuclear
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GeneratingStation)
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CONFIRMATORY ORDER I
The Sacramento Municipal Utility District (the Licensee) is the holder of Facility Operating License No. DPR-54 which authorizes the Licensee to operate the Rancho Seco Nuclear Generating Station (the facility) at power levels not in excess of 2,772 megawatts thermal.
The facility is a pressurized water reactor located at the Licensee's site in Sacranento County, California.
II Following the incident of February 26, 1980, at the Crystal River facility, the NRC staff held meetings with the Licensee, other operating licensees with Babcock and Wilcox (B&W) reactor systems, and B&W. The meetings were held in Bethesda, Maryland on March 4,17 and 18,1980. These meetings resulted in the development of three licensee connitments.
1.
Actions which will allow the operator to cope with various combinations of loss of instrumentation and control functions.
This includes changes in (A) equipment and control systems to give clear indications of functions which are lost or unreliable; (B) procedures and training to assure posi-tive and safe manual response by the operator in the event that competent instruments are unavailable.
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,l 2.
Determination of the effects of various combinations of loss of instru-mentation and control functions by design review analysis and verification by test.
3.
Correction of electrical deficiencies which may allow the power operated relief valve and pressurizer spray valve to open on non-nuclear instru-mentation power failures, such as, the event which occurred at Crystal River, Unit 3 on February 26, 1980.
The Licensee confirmed by letter dated March 21, 1980, that it would inplement all three actions at its facility prior to the restart of Rancho Seco which is currently shutdown for maintenance and refueling. The March 21 letter included by reference the licensee's submittal of March 12, 1980; the March 12 letter provided the detailed listing of various comtinations of loss of instrumentation which constitutes the comit-ment in Item 1 and the ?etter also provided the specific list of tests which constitutes the comitment in Item 2.
I have concluded that timely implementation of these three short term actions, at operating B&W system nuclear power plants is necessary to provide n
continued assurance of public health and safety.
III in view of the importance of this matter I have determined that these comitments be formalized by order and that the public health, safety and interest require that this Order be made immediately effective.
Accordingly, pursuant to the Atomic Energy Act of 1954, as amended, and the Comission's regulations in 10 CFR Parts 2 and 50, IT IS HEREBY ORDERED, EFFECTIVE IMMEEIATELY, THAT:
The Licensee prior to restart after the current outage will implement all three actions provided in Part II of this Order.
IV Any person whn has an interest affected by this Order may request a hearing within twenty-five days of the date of the Order.
Any request for a hearing will not stay the effectiveness of this Order.
A y request for a hearing shall be submitted to the Director, Office of Nuclear Reactor Regulation, U. S. Nuclear Regulatory Comission,
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3, Washington, D. C.
20555, with a copy to the Executive Legal Director at the above address.
If a hearing is requested by a person who has an interest affected by this Order, the Connission will issue an Order designating the time and place of any such hea ri ng.
In the event any person who has an interest affected by this Order requests a hearing as provided above and a hearing is held, the issues to be considered at such a hearing shall be:
(1) Whether the facts set forth in Part II of this Order provide an adequate basis for the actions ordered, and (2) Whether the Licensee should perfonn the actions required by Part III i
of this Order in accordance with the schedule stated therein.
Operation of the facility on terms consistent with this Order is not stayed by the pendency of any proceedings on the Order.
FOR THE NUCLEAR REGULATORY COMMISSION f41h
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Harold R. Denton, Director Office of Nuclear Reactor RegLletian Dated at Bethesda, Maryland this 14thday of April 1980, i
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