ML20024J263
| ML20024J263 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/05/1994 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20024J262 | List: |
| References | |
| 50-313-94-07, 50-313-94-7, NUDOCS 9410130110 | |
| Download: ML20024J263 (2) | |
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APPENDIX A NOTICE OF VIOLATION Entergy Operations, Inc.
Docket:
50-313 Arkansas Nuclear One License:
DPR-51 During an NRC inspection conducted on July 24 through September 3, 1994, one 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:
i A.
Technical Specification 3.6.5 requires that, prior to criticality following a refueling shutdown, a check shall be made to confirm that all manual reactor building isolation valves which should be closed are closed and locked, as required.
10 CFR Part 50, Appendix A, General Design Criteria 57, " Closed System Isolation Valves," requires that each line that penetrates primary reactor containment and is neither part of the reactor coolant pressure boundary nor connected to the containment atmosphere shall have at least one containment isolation valve which shall be either automatic, locked closed, or capable of remote manual operation.
l Safety Analysis Report, Section 1.4.50, " Criterion 57 - Closed System Isolation Valves," states, in part, " Penetration and valving design meets the intent of this criterion."
Feedwater Valves FW-1039 and FW-1048 are manual reactor building isolation valves for lines penetrating reactor building Penetrations P-3 and P-4.
Safety Analysis Report, Section 5.2.2.4.1, lists exceptions to the isolation requirements of General Design Criteria 54, 55, 56, and 57; however, Feedwater Penetrations P-3 and P-4 are not listed as an exception to General Design Criteria 57.
1.
Contrary to the above, on September 2, 1994, the inspector discovered that Feedwater Valves FW-1039 and FW-1048 were closed, but not locked.
2.
Contrary to the above, as of September 3, 1994, Feedwater Valves FW-1039 and FW-1048 were not included in Procedure 1102.001, " Plant Preheatup and Precritical Checklist."
This is a Severity Level IV violation (Supplement 1) (313/9407-01).
Pursuant to the provisions of 10 CFR 2.201, Entergy Operations, Inc. is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.C. 20555 i
with a copy to the Regional Administrator, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, and a ccpy 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 f c r 9410130110 941005 PDR ADOCK 05000313 G
- 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 a Demand for Information may be issued to show cause 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 Arlingt n. Texas, this 5ti(s day of 1994
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