ML20205A486

Notice of Violation from Insp on 860609-13

ML20205A486
Person / Time
Site:	McGuire, Mcguire
Issue date:	08/05/1986
From:	Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20205A477	List: ML20205A473 ML20205A486 ML20205A496
References
50-370-86-16, NUDOCS 8608110382
Download: ML20205A486 (2)

Text

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I ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket No. 50-370 McGuire License No. NPF-17 During the Nuclear Regulatory Commission (NRC) inspection conducted on June 9-13, 1986, a violation of NRC requirements was identified. The violation involved failure to determine the as-found leak rate of the Unit 2 primary containment.

In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985), the violation is listed below:

Technical Specification 4.6.1.2 requires that containment leakage rates be determined in conformance with the requirements of Appendix J to 10 CFR 50 and ANSI N45.4-1972.

10 CFR 50, Appendix J, paragraph III. A.3(a), requires all containment integrated leak rate (Type A) tests be conducted in accordance with the provisions of ANSI N45.4-1972.

ANSI N45.4-1972, paragraph 4.2, requires that periodic containment integrated leak rate tests (CILRT) shall be conducted before any preparatory repairs are made in order to disclose the normal state of repair (as-found condition) of the containment.

10 CFR 50, Appendix J, paragraph III.A.1 requires that in the event repairs and/or adjustments are made to the containment leakage barrier prior to the final CILRT, the change in leakage rate due to these repairs and/or adjustments shall be determined using local leak rate test (LLRT) methods and the overall integrated leakage determined from the LLRT and CILRT results.

Contrary to the above, during the Unit 2, June 1986 refueling outage, the licensee performed repairs or adjustments (preventive maintenance) on an estimated 50% of the containment isolation valves prior to the Type A test but failed to determine the change in leakage as a result of these repairs or adjustments to determine the as-found containment leak rate.

This is a Severity Level IV violation (Supplement I).

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Duke Power Company Docket No. 50-370 McGuire 2 License No. NPF-17 Pursuant to the provisions of 10 CFR 2.201, Duke Power Company 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: (1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION Roger D. Walker, Director Division of Reactor Projects Dated at Atlanta, Georgia this RA day of h%dRf 1986 0

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