ML20043D265
| ML20043D265 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/22/1990 |
| From: | Julian C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20043D264 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 50-302-90-15, NUDOCS 9006070315 | |
| Download: ML20043D265 (1) | |
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ENCLOSURE 1 NOTICE OF DEVIATION Florida Power Corporation Docket No. 50-302 Crystal River License No. DPR-72 The following deviation was identified durino a Nuclear Regulatory Commission (NRC) inspection conducted on April 23-27, 1990.
In florida Power Corporation submittal "NUREG 0737 Supplement 1, i
Regulatory Guide 1.97", transmitted March 21, 1988, they committed to comply with Regulatory Guide (RG) 1.97
" Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident", unless specific exceptions were described.
One of the design criteria stipulated in RG 1.97 states: Types A, B, and C instruments designated as Categories 1 and 2 should be specifically identified with a common designation on the control panels so that the operator can easily discern that they are intended for use under accident conditions.
Contrary to the above, Crystal River 3 does not have the stipulated common designation of instruments on the control panels, and exception was not taken to this design criteria in any submittal.
The March 21, 1988, submittal indicates the plant was in compliance with RG 1.97 at the time of the submittal.
Please provide to the U.S. Nuclear Regulatory Commission. ATTN:
Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, Crystal River, in writing within 30 days of the date of this Notice, the reasons for the deviation, the corrective steps which have been taken and the results achieved, the corrective steps which will be taken to avoid further deviations, and the date when your corrective action will be completed.
Where good cause is shown, consideration will be given to extending the. response time.
FOR THE NUCLEAR REGULATORY COMMISSION
- h. A -
Jan y
Caudie A. Julian, Chief Engineering Branch Division of Reactor Safety Dated at Atlanta, Georgia this22nd day of May 1990
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