ML19257B819
| ML19257B819 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/02/1980 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | FLORIDA POWER CORP. |
| Shared Package | |
| ML19257B816 | List: |
| References | |
| NUDOCS 8001180427 | |
| Download: ML19257B819 (4) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
)
Florida Power Corporation Docket No. 50-302
)
(Crystal River Unit No. 3)
)
)
ORDER TO SHOW CAUSE I
The Florida Power Corporation (the Licensee) is the holder of Facility Operating License No. DPR-72 which authorizes the Licensee to operate the Crystal River Nuclear Power Plant, Unit No. 3 at power levels not in excess of 2452 megawatts themal (rated power). The facility is a pressurized water reactor located at the Licensee's site in Citrus County, Florida.
II Following the Three Mile Island Unit 2 (TMI-2) accident on March 28, 1979, a TMI-2 Lessons Learned Task Force of the Nuclear Regulatory Commission (NRC)
Staff conducted an intensive review of the design and operational aspects of nuclear power plants and the emergency procedures for coping with potential accidents. The Task Force identified measures to be taken in the short-term to reduce the likelihood of accidents and to improve emergency preparedness in responding to accidents.
These measures are set forth in NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-term Recomendations".
The 1770 162 8001180 O
d.
em
. NRC has concluded that prompt implementation of the actions denominated
" Category A" requirements at operating nuclear power plants is necessary to provide continued assurance of public health and safety. These " Category A" requirements were transmitted to all licensees operating nuclear power plants by letter dated September 13, 1979. By letter to affected licensees dated October 30, 1979, further clarification of these requirements was provided.
III The Licensee has comitted to implementation of each " Category A" require-ment albeit not in all cases prior to January 31, 1980. NUREG-0578 and my letters of September 13 and October 30, 1979, which are hereby incorporated into this Order by reference, describe in detail the basis for implementing " Category A" requi rements. The majority of licensees have enn:itted to implement the
" Category A" requirements by January 31, 1980 or the reactor will shutdown until such implementation is complete. However, other licensees have indicated that additional necessary equipment, which is on order, will be delivered after this date. Thirty days after delivery of equipment is a practical time period during which the equipment can be installed. Based on available information, all equipment should be delivered and capable of being installed by June 1, 1980. Licensees are required to meet the January 31, 1980 schedule unless they adequately demonstrate, in accordance with this Order, tha.t delay, based on equipment availability is justified. Available information 4 %%.;
- 779 ;g3
-4 indicates that the Florida bulk power system is currently encountering reliability p roblems.
In view of the potential adverse impact of multiple nuclear plant shutdowns on power reliability in the Southeastern Electric Reliability Council, I have detemined that a two week extension to February 15, 1980, for nuclear facilities in this Council is justified to pemit staggering of plant shutdowns.
For reasons discussed, timely inplementation of these requirements is necessary to provide continued assurance of public health and safety. Requirements should be satisfied as soon as practicable and in no instance shall a licensee with incomplete " Category A" actions continue operation beyond June 1,1980.
IV 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 THAT the Licensee show cause, in the manner hereinafter provided, why it should not:
By February 15, 1980, implement all " Category A" requirements (except the requirement of 2.1.7.a of NUREG-0578) referred to in Part II of this Order, except those for which necessary equipment is shown, by appropriate and timely documentation to the Director, Office of NRR, to be unavailable, or place and maintain its facilities in a cold shutdown or refueling mode of operation unless shutdown would severely impact the power reliability in the Florida subregion of the Southeastern Electric Reliability Council by requiring more than one nuclear plant within the subregion to be shutdown at the same time, as shown by appropriate and timely 1770 164' documentation to the Director, Office of NRR. " Category A" requirements not implemented by February 15,1980, owing to the unavailability of necessary equipment shall be implemented within 30 days of the date such equipment becomes available.
All " Category A" requirements must be implemented no later than June 1,1980.
In view of the importance of the prompt implementation of " Category A" requirements to the health and safety of the public, I have detemined that the public health, safety or interest requires that this Order be temporarily effective as of this date, pending further Order of the Comission.
V The Licensee may file a written answer to this Order under oath or affimation within twenty (20) days of the date of the Order. The Licensee or any other persen whose interest may be affected by this Order may request a hearing within twenty (20) days of the date of the Order.
Any request for a hearing will not stay the temporary effectiveness of this Order. Any request for a hearing shall be addressed to the Director, Office of Nuclear Reactor Regulation, U. S. Nuclear Regulatory Comission, Washington, D. C.,
20555.
If a hearing is requested by a person whose interest may be affected by this Order, the Commission will issue an Order designating the time and place of any such hearing.
1770 165
. In light of the Licensee's expressed willingness to implement " Category A" requirements, except as indicated in Part III of this Order, in the event a hearing is requested, the issue to be considered at such hearing shall be:
whether all " Category A" requirements (except the requirements of 2.1.7.a of NUREG-0578) should be implemented in accordance with the schedule prescribed by this Order.
Operation of the facility on tenns consistent with this Order is not stayed by the pendency of any proceedings on the Order.
FOR THE NUCLEAR REGULATORY COMMISSION MS Harold R. Denton, Director Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 2nd day of January,1980 1770 l'66
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