ML15112A919
| ML15112A919 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/17/1980 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | DUKE POWER CO. |
| Shared Package | |
| ML15112A921 | List: |
| References | |
| NUDOCS 8005120097 | |
| Download: ML15112A919 (4) | |
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80512009q7 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Duke Power Company Dockets Nos. 50-269, 50-270 and 50-287 (Oconee Nuclear Station, Units
)
Nos. 1, 2 and 3)
CONFIRMATORY ORDER The Duke Power Company.(the Licensee) is the holder of Facility Operating Licenses Nos. DPR-38, DPR-47 and DPR-55 which authorize the Licensee to operate the Oconee Nuclear Station, Units Nos. 1, 2 and 3 (the facilities) at power levels not in excess of 2,568 megawatts thermal for each unit.. The facilities are pressurized water reactors located at the Licensee's site in Oconee County, South Carolina.
Following the incident of February 26, 1980, at the Crystal River Unit No. 3 Nuclear Generating Plant, 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 actions.
- 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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- 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 stated by letters dated March 24 and 28, and April 14, 1980, that it has already implemented some and has confirmed that except for the testing of Unit 1 as specified in Action 2 above it would implement the remainder of the three actions at the facilities. The Licensee states that it will test Unit 1 if the results of the tests on Units Nos. 2 and 3 indicate that a test of Unit 1 is needed. The April 14 letter provided a listing of the non-nuclear operating parameters needed by the plant operators in order to place the plant in a safe hot shutdown condition in accordance with the commitment in Action 1. The April 14 letter also provided the specific list of tests which constitutes the commitment in Action 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 continued assurance of public health and safety.
III In view of the importance of this matter I have determined that these commit ments 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 Commission's regulations in 10 CFR Parts 2 and 50, IT IS HEREBY ORDERED, EFFECTIVE IMMEDIATELY, THAT:
(1) The Licensee shall implement at Oconee Nuclear Station, Units Nos. l, 2 and 3 all the three actions provided in Part II of this Order except the testing of Unit No. 1.
-3 (2) The Licensee shall perform a verification test on Unit No. I if the results of the tests on Units Nos. 2 and 3 do not confirm the effects of various combinations of loss of instrumentation and control functions as determined by the design review analysis on Units Nos. 2 and 3, (3) The Licensee shall complete the above requirements within 90 days after the date of this Order or in the alternative, place and maintain each facility for which this Order is not completed in a cold shutdown or refueling mode of operation.
IV Any person who 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. Any request for a hearing shall be submitted to the Director, Office of Nuclear Reactor Regulation, U. S. Nuclear Regulatory Commission, 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 Commission will issue an Order designating the time and place of any such hearing.
-4 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 perform the actions in Part III of this Order in accordance with the schedule stated therein.
Operation of the facilities on terms consistent with this Order is not stayed by the pendency of any proceedings on the Order.
FOR THE NUCLEAR REGULATORY COMMISSION Harold R. Denton, Director Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 17thday of April 1980.