ML20057C323
| ML20057C323 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/09/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20057C317 | List: |
| References | |
| 50-302-93-21, NUDOCS 9309280216 | |
| Download: ML20057C323 (2) | |
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9 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 July 11 - August 14, 1993, a violation of NRC requirements was identified.
In accordance with the " General Statement i
of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violation is listed below:
10 CFR 50, Appendix B, Criterion XVI, Corrective Action, and the licensee's accepted Quality Assurance Program, FSAR, Chapter 1, require that measures be established to assure that conditions adverse to i
quality are promptly identified and corrected.
In'the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition. The licensee's letter to the NRC of June 22, 1993, in response to Notice of Violation 50-302/93-09-01, stated that the inadequate locally posted instructions for manual operation of Decay Heat Closed Cycle Cooling Heat Exchanger Outlet Valve (DCV-177) have been replaced with interim instructions for taking manual control of the valve without repositioning.
Contrary to the above, measures did not assure corrective actions would preclude repetition of the Reactor Coolant System overcooling event of March 5, 1993. On August 11, 1993, the licensee's interim corrective actions described in response to Violation 50-302/93-09-01 were inadequate in that the revised interim instructions for taking manual control of DCV-177 could not be performed with the valve in a mid-position (as required to prevent a system overcooling transient). With the valve in a mid-position, a steel plate prevented the performance of step three of the instructions (removal of the valve stem pin).
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.
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, 9309280216 930909 PDR ADOCK 05000302 O
Florida Power Corporation 2
Docket No. 50-302 Crystal River Unit 3 License No. DPR-72 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 A Atlanta, Georgia this 11f) day of September 1993 l
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