IR 05000817/2009016

Notice of Violation from Insp on 850817-0916

ML20138A358
Person / Time
Site:	Grand Gulf, 05000817
Issue date:	09/27/1985
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20138A345	List: IR 05000416/1985033 IR 05000817/2009016 ML20138A341
References
50-416-85-33, NUDOCS 8510080535
Download: ML20138A358 (2)

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ENCLOSURE 1 NOTICE OF VIOLATION l

I Mississippi Power and Light Company Docket No. 50-416 Grand Gulf License No. NPF-29 The following violations were identified during an inspection conducted on August 17 - September 16, 1985. The Severity levels were assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C). Technical Specification Surveillance requirements 4.6.1.3.b and 4.6.2. require that an overall leakage test of each containment and drywell air lock be conducted at least once per 6 months to verify the overall air lock's leakage rate is within its limi Contrary to the above the containment and drywell air locks were not totally tested for overal'1 leakage rate in that the test port flanges removed to ,

perform the air locks test were not leak rate tested after reinstallatio These flanges were leak rate tested for the first time on June 21, 1985, for the containment air locks and June 27, 1985 for the drywell air lock This is a Severity Level IV violation (Supplement I). , CFR 50.73 requires that the licensee shall submit a Licensee Event Report (LER) for any event described in part 50.73 within 30 days af ter the disccvery of the even Contrary to the above on June 21, 1985, the Plant Safety Review Committee (PSRC) discovered that the drywell and containment air lock test port flanges were not being local leak rate tested (LLRT) as required by 10 CFR 50, Appendix J. This requirement for LLRT was reviewed by Nuclear Plant Engineering and confirmed in a PSRC meeting on June 21, 198 LER 85-026 ias not submitted to the NRC until August 7, 1985, exceeding the 30 day reporting criteria.

l l This is Severity Level IV violation (supplement I).

I CFR 50, Appendix B, Criterion XVI as implemented by the licensee's Operational Quality Assurance Manual (MPL-TOP-1A), Policy 16, requires procedures be established that provide for the evaluation of conditions such j as nonconformances, failures, malfunctions, deficiencies, violations, deviations, reportable occurrences,10 CFR 21 items, and defective material and equipment to determine the need for corrective action and to identify possible adverse quality trends. Administrative Procedure ( AP) 01-S-03-1, GGNS Quality Program, Paragraph 6.1.10.c states that Plant Incident Reports shall be used to report and evaluate incidents involving equipment failures, personnel errors and procedural deficiencies which detrimentally affect nuclear safet DR ADOCK O y

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f Mississippi Power and Light Company 2 Docket No. 50-416 Grand Gulf License No. NPF-29 Contrary to the above on August 19, 1985, when the operability of SRV F051B was in question, a Plant Incident Report was not initiate This is a Severity Level IV violation (Supplement I).

Pursuant to 10 CFR 2.201, you are required to submit to this office within 30 days of the date of this Not-ice, a written statement or explanation in reply, including: (1) admission or c?nial 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 SEP 2 / 135 Date:

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