ML20147B768

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Notice of Violation from Insp on 961201-970111.Violation Noted:On 961206,shift Supervisor Documented Operability Determination for turbine-driven Auxiliary Feedwater Pump Identifying Governor Oil Result
ML20147B768
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 01/30/1997
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20147B763 List:
References
50-482-96-24, NUDOCS 9702030155
Download: ML20147B768 (2)


Text

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E_N_ CLOSURE 1 NOTICE OF VIOLATION Wolf Creek Nuclear Operating Corporation Docket No.: 50-482 Wolf Creek Generating Station License No.: NPF-42 During an NRC inspection conducted on December 1,1996, through January 11,1997, four 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. Criterion V of Appendix B to 10 CFR Part 50 requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, and drawings appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.

Procedure ADM 02-024 requires operability determinations to include a determination of the requirement or commitment established for the equipment.

Contrary to the above, on December 6,1996, at 2:38 p.m., the shift supervisor documented an operability determMation for the turbine-driven auxiliary feedwater pump that identified a governor oil sample result of 3915 ppm water, but failed to acknowledge the vendor's technical manuallimit of 5000 ppm and an intrusion rate  ;

of spproximately 700 ppm per hour.

This is a Severity Level IV violation (Supplement 1) (482/9624-01).

B. Technical Specification 6.8.1.a. states, in part, that written procedures shall be l established and implemented covering the applicable procedures recommended in 1 Appendix A of Regulatory Guide 1.33, Revision 2.

Regulatory Guide 1.33, Appendix A, Section 8.b.(1)(x), requires procedures for surveillance tests of main steam safety valves.

Surveillance Procedure STS MT-008, " Main Steam Safety Valve Settings,"

Revision 5, Step 7.11.1, required workers to install the spindle nut and spindle nut cotter pin.

Contrary to the above, on March 3,1993, maintenance workers failed to install the spindle nut cotter pin on Valve AB UV0046.

This is a Severity Level IV violation (Supplement I) (482/9624-02).

C. 10 CFR 50.59 requires, in part, that licensees maintain a written safety evaluation which provides the basas for the determination that the change does not involve an unreviewed safety question.

9702030155 970130 PDR ADOCK 05000492 G PDR

l 2-Contrary to the above, on July 3,1996, the licensee changed Section 16.3.1.5 and other sections of the Updated Safety Analysis Report without documenting an adequate basis that an unreviewed safety question was not involved in that the unreviewed safety question determination contained substantive errors.

This is a Severity IV violation (Supplement I) (482/9624-05).

Pursuant to the provisions of 10 CFR 2.201, Wolf Creek Nuclear Operating Corporatior, 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 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). Tnis 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 will be given to extending the response time.

Because your response will be placed in the NRC Public Docurnent Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards i 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 ,

I 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 puulic.

Dated at Arlington, Texas this 30th day of Januer, 1997 l l

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