ML20149M597

Notice of Violation from Insp on 871209-880129.Violation Noted:Failure to Take Corrective Actions to Resolve 870818 Violation of Tech Spec Table 3.1.1

ML20149M597
Person / Time
Site:	Dresden
Issue date:	02/18/1988
From:	Forney W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20149M594	List: IR 05000010/1988002 ML20149M593 ML20149M597
References
50-237-87-40, 50-249-87-39, NUDOCS 8802260149
Download: ML20149M597 (1)

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4 NOTICE OF VIOLATION Commorwealth Edison Company Docket No. 50-237 Docket No. 50-249 As a result of the inspection conducted on December 9, 1987 through January 29, 1988, and in accordance with the General Policy and Procedure for NRC Enforcement Actions, (10 CFR Part 2, Appendix C), the following violation was identified:

10 CFR 50, Appendix B, Criterion XVI, as implemented by CECO Topical Report CE-1-A, "Quality Assurance Program for Nuclear Generating Stations", and CECO Corporate Quality Assurance Manual, Nuclear Generating Stations, "Quality Requirement Section 16.0", requires that corrective actions identified from nonconformances, incidents and deviations are verified for satisfactory completion to preclude repetition.

Contrary to the above, the corrective actions taken to resolve an August 18, 1987, violation of Technical Specification Table 3.1.1, which requires a minimum of two operable APRM downscale/IRM high high or inoperable trip functions per Reactor Protection System channel were not effective in preventing a second identical violation of this Technical Specification requirement which occurred four months later on December 18, 1987.

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

Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each violation: (1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid ,

further violations; and (3) the date when full compliance will be achieved.

Consideration may be given to extending your response time for good cause shown.

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5E91 I 5 ,f'f pp Date W. L. Forney, Chief ' '

Reactor Projects Branch 1 kh No G