ML20127E467

Notice of Violation from Insp on 850301-31

ML20127E467
Person / Time
Site:	Brunswick
Issue date:	05/06/1985
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20127E462	List: ML20127E459 ML20127E467 ML20127E517
References
50-325-85-05, 50-325-85-5, NUDOCS 8505200091
Download: ML20127E467 (2)

Text

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s ENCLOSURE 1 NOTICE OF VIOLATION Carolina Power and Light Company Docket No. 50-325 Brunswick 1 License No. DPR-71 The following violation was identified during an inspection conducted on March 1-31, 1985. The Severity Level was assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).

Technical Specificatiori 6.8.1(c) requires that written procedures be imple-mented for surveillance and test activities of safety-related equipment.

Contrary to the above, the Licensee did not implement PT 1.1.7PC in that step VII D.3.(a) was not completed upon resumption of the surveillance test after an 8-hour postponement. Consequently, Average Power Range Monitors were not bypassed during the individual Local Power Range Monitors calibra-

. tion resulting in a half Reactor Protection System trip.

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 Notice, a written statement or explanation in reply, including: (1) admission or denial 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) tne date when full compliance will be achieved.

Security or safeguards information should be submitted as an enclosure to facili-tate withholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73.21.

MAY 6 1985 Date:

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ENCLOSURE 1 NOTICE OF VIOLATION Carolina Power and Light Company Docket No. 50-325 Brunswick 1 License No. DPR-71 The following violation was identified during an inspection conducted on March 1-31, 1985. The Severity Level was assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).

Technical Specification 6.8.1(c) requires that written procedures be imple-mented for surveillance and test activities of safety-related equipment.

Contrary to the above, the Licensee did not implement PT 1.1.7PC in that step VII D.3.(a) was not completed upon resumption of the surveillance test after an 8-hour postponement. Consequently, Average Power Range Monitors were not bypassed during the individual Local _ Power Range Monitors calibra-tion resulting in a half Reactor Protection System trip.

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 Notice, a written statement or explanation in reply, including: (1) admission or denial 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 achieved.

Security or safeguards information should be submitted as an enclosure to facili-tate withholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73.21.

Date: