ML20135E096
| ML20135E096 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/28/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20135E089 | List: |
| References | |
| 50-313-96-09, 50-313-96-9, NUDOCS 9703060255 | |
| Download: ML20135E096 (2) | |
Text
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ENCLOSURE 1 NOTICE OF VIOLATION Entergy Operations, Inc.
Docket No.:
50-313 Arkansas Nuclear One License No.:
DPR-51 During an NRC inspection conducted on December 22,1996, through February 1,1997, two violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:
A.
Unit 1 Technical Specification 6.8.1 states, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures i
recommended in Appendix A of Regulatory Guide 1.33, November 1972.
Paragraph A.3 of Regulatory Guide 1.33, November 1972, states, in part, that equipment control (e.g., locking and tagging) should be covered by written procedures.
Procedure 1000.027, Revision 22, " Hold and Caution Card Control," Step 6.9.2, directs the shift superintendent / control room supervisor to verify, prior to authorizing hold card removal and system restoration, that the signature of the lead craftsman has been obtained, signifying release of the hold cards for the work activity.
Contrary to the above, on January 13, the Unit 1 control room supervisor failed to verify that the lead craftsman had signed the Hold Card Authorization form prior to authorizing the removal of the hold card and restoration of Breaker A-104 to the closed position. This resulted in a near-miss accident, since electricians were working in 480v Bus B14 at the time it was reenergized.
This is a Severity Level IV violation (Supp!oment 1) (Violation 50-313/9609-01).
B.
10 CFR 50.71(e) states, in part, that "each person licensed to operate a nuclear power reactor shall update, periodically... the Final Safety Analysis Report (FSAR) originally submitted as part of the application for the operating license to assure that the information included in the FSAR contains the latest material developed....
The updated FSAR shall be revised to include the effects of all changes made in the f acility or procedures as described in the FSAR...."
Contrary to the above, the Unit 1 FSAR was not revised to incorporate the installation of fibrous insulation on Reactor Coolant Pumps A and B in October 1993.
g This is a Severity Level IV violation (Supplement 1) (Violation 50-313/9609-02).
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,
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l 9703060255 970228 PDR ADOCK 05000313 l
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. - ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, 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 correct;ve steps that will be taken to avoid further violations, and (4) the date when full
. compliance will be achieved. Your response may reference or include previous docketed correspondence,if the correspondence adequately addresses the required response. If an adequate reply is not received within the time specified in this Notice, an order or a 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.
Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards 1
information so that it can be placed in the PDR without redaction. However, if you find it I
necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public.
Dated at Arlington, Texas, this 28th day of February 1997 l
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