ML20207M982

Notice of Violation from Insp on 861009-1204

ML20207M982
Person / Time
Site:	Quad Cities
Issue date:	01/08/1987
From:	Paperiello C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20207M969	List: IR 05000254/1986016 ML20207M968 ML20207M982
References
50-254-86-16, 50-265-86-16, NUDOCS 8701130366
Download: ML20207M982 (2)

Text

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o l NOTICE OF VIOLATION Commonwealth Edison Company Docket Nos. 50-254; 50-265 As a result of the inspection conducted on October 9 through December 4,1986, and in accordance with the " General Policy and Procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985), the following violation was identified:

1. 10 CFR 50, Appendix B, Criterion XVI, as implemented by the Comonwealth Edison Company (CECO) Quality Assurance Manual, Quality Requirement 16.0, requires that a corrective action system will be used to assure that such items as failures, malfunctions, deficiencies, deviations, defective material and equipment and programmatic deficiencies which are adverse to quality and might affect the safe operation of a nuclear generating station are promptly identified and corrected.

Contrary to the above, the licensee's measures were not adequate to assure that the causes of excessively leaking containrrent isolation valves and penetrations were determined and that corrective action was taken to preclude repetition. As a consequence, the combined leakage for valves and penetrations subject to Type B and C tests exceeded the 10 CFR 50, Appendix J Criterion of 0.6La, for the last four Unit 1 outages (1979, 1982, 1984 and 1986) and for the last eight Unit 2 outages (1974, 1976, 1978, 1979, 1981, 1983, 1985 and 1986).

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

2. 10 CFR 50, Appendix B, Criterion. XVII, as implemented by CECO Quality Assurance Manual, Quality Requirement 17.0, requires that Quality Assurance records include items which are related to the safe operation of the Station; which document the repair or modification of station equipment; and which provide inspection data for results of reviews, tests and material analysis.

Contrary to the above, the drywell head flange gasket was changed from one recommended by the flange designer, Chicago Bridge and Iron, and made of Garlock Material No. 8364, to one made by J-BAR Incorporated, Compound No. 3301, without documented evidence of a design evaluation or material analysis review to determine whether the gasket materials were compatible.

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

With respect to Item 1, the inspection showed that action had been taken to correct the identified violation and to prevent recurrence. Consequently, no reply to the violation is required and we have no further questions regarding this matter. With respect to Item 2, pursuant to the provisions of hb G

Notice of Violation 2 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.

Dated l- f ~ f 7 Lb n, l Carl'f. F4peripilo, Director Division of Reactor Safety a