IR 05000421/2005020

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Notice of Violation from Insp on 850421-0520
ML20133P708
Person / Time
Site: McGuire, 05000421, Mcguire  Duke Energy icon.png
Issue date: 07/23/1985
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20133P702 List:
References
50-369-85-16, 50-370-85-17, NUDOCS 8508140429
Download: ML20133P708 (2)


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I JUL 2 31985 ENCLOSURE 1 NOTICE _0F VIOLATION Ouke Power Company Docket Nos. 50-369 and 50-370 McGuire Nuclear Station License Nos. NPF-9 and NPF-17 The following violations were identified during an inspection conducted on April 21 - May 20,198 The Severity Levels were assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C). Technical Specification 6.8.1 requires that written procedures be estab-lished, implemented and maintained covering the activities referenced in Appendix A of Regulatory Guide 1.33, Revision 2, 1978 including but not limited to:

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control of the removal and restoration of safety-related equipment

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operation of safety-related equipment Contrary to the above: On April 15, 1985, Removal and Restoration (R&R) 5866 was cleared without returning the associated main steam line drain valves to service resulting in a main steam line water hammer, On May 2, 1985, an unlabeled valve, 2NI-340, was operated instead of the procedurally required valve 2NI-297 which resulted in the rupture of the upper head injection (UHI) sightglass, On April 20, 1985, the procedural requirement to remove f rom contain-ment loose debris, trash, and/or plastic which could be transported to the containment sump causing a restriction was violated in that the procedure step was signed of f on April 20, yet on April 24, during a containment tour, the inspector noted that an inordinate quantity of aforementioned potential sump restrictions were in containmen This is a Severity Level IV violation (Supplement 1) applicable to Unit . 10 CFR 50, Appendix B, Criterion III, Design Control; Criterion Instructions, Procedures; and Criterion X, Inspection, as implemented by Topical Report Duke-1-A, require that: Measures be established to assure that applicable regulatory require-ments and the design basis for safety-related structures, systems, and components are correctly translated into specifications, drawings, procedures, and instructions. These measures shall include provisions to assure that appropriate quality standards are specified and included 0500140429 050723 PDR ADOCK0500g9

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Duke Power Company 2 Docket Nos. 50-369 and 50-370 McGuire Nuclear Station License Nos. NPF-9 and NPF-17

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in design documents and that deviations from such standards are controlled, Instructions, procedures, or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplishe A program for inspection of these activities be established and executed to verify conformance with the documented instructions, procedures, and drawings for accomplishing the activity to assure conformanc Contrary to the above:

(1) Inadequate measures, procedures, or instructions were taken or provided to assure that the requirements of the design specification MSC 139.01-00-007, under which certain of the Unit I and Unit 2 safety-related valves / motors were installed, were implemente Specifically, thermal overload protection circuitry had not been modified by installation of shorting bars and circuitry on specified valve (2) The inspection program to verify conformance with regulatory require-ments was inadequate, in that it did not detect the deficient measures or installation for assuring design specification MSC 139.01-007 conformanc This is a Severity Level IV Violation (Supplement 1).

Pursuant to 10 CFR 2.201, you are required to submit to this office within 30 days of the date of this Notice, a written statement or explanation in reply, including: (1) admission or dental of the alleged violations; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further violations; and (5) the date when full compliance will be achieve Security or safeguards information should be submitted as an enclosure to facilitate withholding it from public disclosure as required by 10 CFR 2.790(d)

or 10 CFR 73.2 'JUL t 31885 Date:

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