ML20151Q911

Notice of Violation from Insp on 880601-0704.Violations Noted:Door H300 Tied Open W/No Fire Watch Posted & Surveillance Procedure Sp 6.3.4.3 Performed W/Core Spray & RHR Injection Valves Energized

ML20151Q911
Person / Time
Site:	Cooper
Issue date:	07/21/1988
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20151Q908	List: ML20151Q904 ML20151Q911 ML20151Q914
References
50-298-88-20, NUDOCS 8808110326
Download: ML20151Q911 (2)

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APPENDIX A NOTICE OF VIOLATION Nebr-aska Public Power District Docket: 50-298 Cooper Nuclear Station License: DPR-46 During an NRC inspection conducted during the period June 1 through July 4, 1988, three violations of NRC requirements were identified. The violations involved failure to post a fire watch, failure to perform adequate valve lineup, and failure to use adequate test instrumentation. In accordance with the "General Statement of Policy and Procedure for NRC Enforce cent Actions,"

10 CFR Part 2, Appendix C (1987), the violations are listed below:

A. Failure to Post a Fire Watch 10 CFR 50, Appendix B, Criterion V, and the 'icensee's approved Quality Assurance Plan, require that activities shall be accomplished in accordance with approved instructions, procedures, and drawings. CNS Procedure 0.16, "Control of Fire Doors," Revision 6, dated May 26, 1988, requires that door H300 have a fire watch whenever it is obstructed so as to prevent it from closing.

Contrary to the above, on June 22, 1988, door H300 was tied open with no tire watch posted.

This is a Severity Level IV violation. (SupplementI)(298/8820-01)

8. Failure to Perform Adequate Valve Lineup 10 CFR 50, Appendix B, Criterien V, and the licensee's approved Quality Assurance Plan require that activities shall be accomplished in accordance with approved instructions, procedures, or drawings. Surveillance Procedure (SP) 6.3.4.3, "Sequential Loading of Emergency Diesel Generators," Revision 24, dated May 19, 1988, Table 2, requires that the core spray (CS) and residual heat removal (RHR) injection valves be shut and deenergized while conducting the test.

Contrary to the above, on June 9, 1988, SP 6.3.4.3 was performed with the CS and RHR injection valves energized. This resulted in the CS and RHR injection valves opening during the test.

This is a Severity Level IV violation. (Supplement I)(298/8820-02)

C. Failure to Use Adequate Test Instrumentation 10 CFR 50, Appendix B, Criterion XI, and the licensee's approved Quality Assurance Plan require that adequate test instrumentation be used to demonstrate that structures, systems, and components will perfonn satisfactorily in service.

8808110326 DR 88072i ADOCK 05000298 PNU o

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Contrary to the above, on June 15 and 18,1988, inadequate instrumentation was utilized in the performance of the 3 psi drywell personnel airlock test of Surveillance Procedure 6.3.1.1 "Primary Containment Local Leak Rate Tests," Revision 22, dated February 22, 1988. The test gauge was accurate to .05 psi with a readability of .05 psi. A pressure drop of less than .01 psi would indicate a failed test.

This is a Severity Level IV violation. (Supplement I)(298/8820-03)

Pursuant to the provisions of 10 CFR 2.201, Nebraska Public Power District is hereby required to submit to this office, within 30 days of the date of the letter transmitting this Notice, a written statement or explanation in reply, including for each violation, (1) the reason for the violation if admitted.

(2) the corrective steps which have been taken and the results achieved, (3) the corrective steps which will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.

Dated at Arlington, Texas this 2 / g day of 1988.

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