ML20029E264
| ML20029E264 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/21/1994 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20029E258 | List: |
| References | |
| 50-302-94-07, 50-302-94-7, NUDOCS 9405180064 | |
| Download: ML20029E264 (2) | |
Text
f ENCLOSURE 1 NOTICE OF VIOLATION Florida Power Corporation Docket No. 50-302 Crystal River Unit 3 License No. DPR-72 During an NRC inspection conducted on March 5 through April 1, 1994, a violation of NRC requirements was identified.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violation is listed below:
Technical Specification 5.6.1.1 and Regulatory Guide 1.33, Appendix A, Revision 2, February 1978, Section 1.c, Equipment Control, require that written procedures be established and implemented to perform safety-related operations.
Regulatory Guide 1.33, Appendix A, includes procedures for operation of safety-related equipment.
Contrary to the above:
(1)
On March 12, 1994, with the reactor in mode 1, Operating Procedure OP-404, Decay Heat Removal System, was not properly implemented in that recirculation valve DHV-18 was found mispositioned in the closed position.
It was discovered that this valve had been closed for approximately one day, following the completion of the maintenance activities.
(2)
On March 17, 1994, with the reactor in mode 1, Operating Procedure OP-707, Operation of the ES Emergency Diesel Generators, was not properly implemented in that the A emergency diesel generator fuel oil day tank drain valve, DFV-2, was found mispositioned in the open position degrading the emergency diesel generator fuel oil system.
Valve DFV-2 had been inadvertently left open since March 14, 1994, following maintenance on the fuel oil day tank level switch DF-2-LS.
(3)
On March 17, 1994, with the reactor in mode 1, Surveillance Procedure SP-169F, Miscellaneous Switch Interlock with Technical Specification Equipment, was not properly implemented in that the isolation valve (no valve number) to pressure transmitter CH-378-PT was found mispositioned in the closed position. This rendered pressure transmitter CH-378-PT, which controls the position of valve CHV-68 (control valve for nuclear services closed cycle cooling to the 1A control complex chiller) inoperable resulting in the control complex chiller being inoperable.
SP-169F, which required that the isolation valve to pressure transmitter CH-378-PT be reopened as part of the restoration, had been performed on March 15, 1994.
This is a Severity Level IV Violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Florida Power Corporation is hereby required to submit a written statement or explanation to the U.S.
i 9405180064 940421
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PDR ADOCK 05000302 i
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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, at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation:
(1) the reason for the violation or,. if contested, the basis for disputing the violation, (2) the corrective steps that have been taken_and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order or demand for information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
Dated at Atlanta, Georgia this 21 day of April 1994