ML20141E323

Notice of Violation from Insp on 970427-0607.Violation Noted:Licensee Failed to Follow Procedure EIP-2-001,in That Licensee Entered TS Limiting Condition for Operation 3.4.5 Upon Determination & Did Not Declare Unusual Event

ML20141E323
Person / Time
Site:	River Bend
Issue date:	06/26/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20141E278	List: IR 05000458/1997008 ML20141E274 ML20141E323
References
50-458-97-08, 50-458-97-8, EA-97-184, NUDOCS 9707010031
Download: ML20141E323 (2)

Text

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ENCLOSURE 1 NOTICE OF VIOLATION Entergy Operations, Inc. Docket No.- 50-458 River Bend Station License No. NPF-47 EA 97-184 During an NRC inspection conducted on April 27 through June 7,1997, 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. 10 CFR 50.54(q) states, in part, that a licensee authorized to possess and operate a nuclear power reactor shall follow and maintain in effect emergency plans that meet the requirements of 10 CFR Part 50, Appendix E.10 CFR Part 50, Appendix E, requires detailed procedures for implementing the emergency plan.

Emergency implementing Procedure EIP-2-001, " Classification of Emergencies,"

Revision 8, implements the requirements of 10 CFR 50.54(q) and 10 CFR Part 50, Appendix E. Emergency Action Level 3 of Procedure EIP-2-001 required the licensee to declare a Notification of Unusual Event upon entry into Technical Specification Limiting Condition for Operation 3.4.5 because of reactor pressure boundary leakage.

1 Contrary to the above, on May 6,1997, the licensee f ailed to follow Procedure EIP-2-001 in that the licensee entered Technical Specification Limiting Condition for Operation 3.4.5 upon determination that pressure boundary leakage i existed, but did not declare a Notification of Unusual Event until prompted by the inspectors on May 7,1997.

This is a Severity Level IV violation (Supplement Vill) (50-458/97008-05).

1 B. Technical Specification 5.4.1.d states, in part, that written procedures shall be l implemented covering fire protection program implementation. '

Fire Protection Procedure FPP-0070, " Duties of Fire Watch," Revision 8, required, in part, the fire watch person to visually inspect each area listed on the patrol fire watch route log.

Contrary to the above, between Ncvember 1,1996, and January 6,1997, one individual failed to complete 105 of his 305 assigned hourly fire watch tours to visually inspect each area listed on the patrol fire watch route log.  ;

I This is a Severity Level IV violation (Supplement I)(50-458/97008-06). l 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 with a copy to the Regional ]

Administrator, Region IV,611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, and a i i

9707010031 970626 POR ADOCK 05000458 G PDR _  ;

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. 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 w'ill 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 information so that it can be placed in the PDR without redaction. However, if you find it necessary to include such information, you should clearly indicate the specific infctmation  ;

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 26th day of June 1997 j

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