ML20126A499

Notice of Violation from Insp on 921011-1121.Violation Noted:Licensee Failed to Change Alr OO-O47E to Provide Alternate Method of Draining Tank

ML20126A499
Person / Time
Site:	Wolf Creek
Issue date:	12/11/1992
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20126A488	List: ML20126A485 ML20126A499 ML20126A503
References
50-482-92-31, NUDOCS 9212210089
Download: ML20126A499 (3)

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. APPENDIX A NOTICE OF VIOLATION Wolf Creek Nuclear Operating Corporation Docket No.: 50-482 Wolf Creek Generating Station License No.: NPF-42 During an NRC in pection conducted October 11 through Novesber 21, 1992, three violations of NRC requirements were identified. In accordance with the

" General Statement of Policy and Procedure for NRC Enforcement Actions,"

10 CFR 2, Appendix C (Enforcement Policy), the violations arn ?isted below:

A. Inadeouate Alarm Response Procedure Technical Specification 6.8.1.a requires that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, dated February 1978. Regulatory Guide 1.33, Appendix A, Item 5, specifies, in part, that alarm procedures should contain guidance for immediate operator action.

Alarm Procedure ALR 00-047E, Revision 4, "RWST LEV HILO," Step 4.4.3, directs personnel to drain the refueling water storage tank to the floor and equipment drain system by using-Valve BN V017, RWST drain valve, Contrary to the above, on October 22, 1992, after determining that the ,

normal drain path from the refueling water storage tank, downstream of Valve BN V017, was blocked by a flange, the licensee failed to change ALR 00-047E to provide an alternate method of draining the tank.

This is a Severity Level IV violation. (Supplement I) (482/9231-01)

8. Inadeouate Postmaintenance Test Instructions Technical Specification 6.8.1.a requires that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, dated February 1978. Regulatory Guide 1.35, Appendix A, Item 9.a, requires that maintenance that affects the performance of safety-related equipment should be properly preplanned and _ performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances. This is accomplished, in part, by:

Procedure ADM 01-057, Revision 25, " Work Request."

Attachment 8, Step 2.A of Procedure ADM 01-057 specifies that postmaintenance testing is used to-verify that the maintenance was--

performed correctly, that the equipment performs its intended function, and that a new deficiency has not been created.

Contrary to the above, the postmaintenance test procedures performed on l September 17, 1992, in accordance with procedures and instructions specified on Work Request 04681-92 did not determine that 9212210099 921211 --

PDR ADOCK 05000482-G PDR

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. Valve BN HV88128, Limit Switch Rotor 3, was not properly adjusted. The misadjustment rendered Valve BB PCV87028 inoperable, which would have prevented placing Train B residual heat removal in-service for long-term hot leg recirculation cooldown, if needed, for approximately 55 days.

This is a Severity level IV violation. (Supplement 1)(482/9231-02)

C. Failure to Properly implement an Approved Procedure Technical Specification 6.8.1.a requires that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, dated February 1978. Regulatory Guide 1.33, Appendix A, Item 3.n, recommends that instructions for startup, shutdown, and changing modes of operation should be prepared, as appropriate, for the chemical and volume control system. This is accomplished, in part, by Procedure SYS BG-201, Revision 15, " Shifting Between Positive Displacement Pump and Centrifugal Charging Pumps."

Step 4.2.6 of Procedure SYS BG-201 requires that operators close Valve BG HV8109, positive displacement pump recirculation valve, when changing the operating pump from a centrifugal charging pump to the positive displacement pump.

Contrary to the above, on October 1,1992, during the implementation of Procedure SYS BG-201, the operator did not perform Step 4.2.6. With Valve BG HV8109 open, a direct path was created from the positive displacement pump to the volume control tank, which resulted in an i approximately 20-second decrease in letdown flow and a loss of charging flow.

This is a Severity Level IV violation. (Supplement I)(482/9231-04)

Pursuant to the provision of 10 CFR Part 2.201, Wolf Creek Nuclear Operating Corporation 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, 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, 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 i

not received within the time specified in this Notice, an order or demand for information may be issued as to why the license should not be modified, L

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suspended, or revoked, or why such o ner 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 A lington exas, this day of M 1992

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