ML20215M713

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Notice of Violation from Insp on 860901-30
ML20215M713
Person / Time
Site: Cooper Entergy icon.png
Issue date: 10/24/1986
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20215M712 List:
References
50-298-86-26, NUDOCS 8611030189
Download: ML20215M713 (2)


Text

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APPENDIX A NOTICE OF VIOLATION Nebraska Public Power District Docket: 50-298 Cooper Nuclear Station License: DPR-46 During an NRC inspection conducted during the period SepteKer 1 through September 30, 1986, violations of NRC requirements were identified. The violations involved failures to follow procedure and to adequately review surveillance test results. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2 Appendix C (1986),

the violations are listed below:

A. Failure to Follow Procedure Appendix B, Criterion V, of 10 CFR Part 50, and the licensee's approved Quality Assurance program require that activities affecting quality be accomplished in accordance with drawings and procedural instructions. CNS Procedure 0.4, " Preparation Review and Approval of Procedures,"

Revision 7, dated July 2, 1986, states that approv_ed. written station procedures shall be adhered to by all station personnel. CNS procedure 2.2.33, "High Pressure Coolant Injection ~ System," Appendix A,

" Valve Checklist," requires that valves HPCI-129 and HPCI-130 be sealed open and valve HPCI-26 to be shut. ,

Contrary to the above, during the performance'of System Operating Procedure 2.2.33, "High Pressure Coolant Injection System," Appendix A.

" Valve Checklist," and during the conduct of Operation Procedure 2.0.2,

" Operations Logs and Report," Section H, " Sealed Valve Log,"

valves HPCI-129 and HPCI-130 valves found open but unsealed, and valve HPCI-26 valve was found open.

This is a Severity Level IV violation. (SupplementI.D)(298/8626-02)

B. Inadequate Review of Surveillance Test Results Appendix B, Criterion XI, of 10 CFR Part 50, and the licensee's approved quality assurance plan, require that test results be documented and evaluated to assure that test requirements have been satisfied. CNS procedure 6.2.4.1P, " Daily Surveillance Log (Technical Specification),

Revision 54, dated July 10, 1986, states, on page 12 of 15, that core spray differential pressure instrumentation be logged and compared to the given acceptable limits of approximately -3.5 psid during normal operation or approximately +3.0 psid in case of a line break.

Contrary to the above, the recorded and accepted values on September 19, 1986, were -28 psid and 9 psid for trains "A" and "B" respectively.

This is a Severity Level IV violation. (Supplement-I.D)(298/8626-03) 89 861024

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2 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 violations 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 p @ day of Oct 1986