ML20129K234

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Notice of Violation from Insp on 960901-1012.Violation Noted:Licensee Used a Pressure Instrument w/full-scale Range That Exceeded Three Times Ref Value or Less
ML20129K234
Person / Time
Site: Waterford Entergy icon.png
Issue date: 11/04/1996
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20129K233 List:
References
50-382-96-12, NUDOCS 9611130066
Download: ML20129K234 (2)


Text

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ENCLOSURE 1 NOTICE OF VIOLATION Entergy Operations, Inc.

Docket No.:

50-382 Waterford Steam Electric Station, Unit 3 License No.:

NPF-38 During an NRC inspection conducted on September 1 through October 12,1996, two violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG4 600, the violations are listed below:

A.

Technical Specification 6.8.1.a requires, in part, that written procedures shall be maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Appendix A, Section 9, requires that the licensee have maintenance procedures.

Procedure OP-903-004, " Boric Acid Pump Operability Check," Section 3.2.4 required, in part, that the full-scale range of pressure instruments be three times the reference value or less.

l Contrary to the above, on September 16,1996, the licensee used a pressure instrument with a full-scale range that exceeded three times the reference value listed in Procedure OP-903-004.

This is a Severity Level IV violation (Supplement 1)(50-382/9612-01) i B.

10 CFR Part 50, Appendix B, Criterion lli states, in part, that measures shall be established to assure that the design basis, as defined in Part 50.2 and, as specified j

i in the license application, are correctly translated into specifications and procedures.

Technical Specification 3.7.1.3 and Updated Final Safety Analysis Report Section 10.4.9 establish the wet cooling tower basins as a backup supply to the emergency feedwater pumps.

Updated Final Safety Analysis Report Section 10.4.9.1 establishes the required inventory for emergency feedwater.

i Updated Final Safety Analysis Report Chapter 15 and the Combustion Engineering l

steam generator technical manual both assume a minimum emergency feedwater temperature of 70*F.

Contrary to the above, as of October 12,1996, the licensee had not established measures to ensure that the design basis was correctly translated into specifications and procedures. Specifically, the backup source of emergency feedwater, wet cooling tower basins, did not have adequate specifications / procedural requirements for maintaining the required inventory or basin temperature, h

i This is a Severity Level IV violation (Supplement I) (50-382/9612-05) 9611130066 961104 PDR ADOCK 05000382 G

PDR 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, l

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 corrective steps that wUl 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 l

adequate reply is not received within the time specified in this Notice, an order or a l

Demand for Information may be issued as to why the license should not be modified, l

suspended, or revoked, or why such othx action as may be proper should not be taken.

I Where good cause is shown, considerafon will be given to extending the response time.

Because your response will be placed its the NRC Public Document Room (PDR), to the l

extent possible, it should not include eny 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 information

)

that you desire not to be placed in the PDR, and provide the legal basis to support your i.

request for withholding the information from the public.

Dated at Arlington, Texas this 4th day of November 1996 j

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