IR 05000625/2008030

Notice of Violation from Insp on 850625-0830

ML20132C712
Person / Time
Site:	Prairie Island, 05000625
Issue date:	09/20/1985
From:	Harrison J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20132C701	List: IR 05000282/1985015 IR 05000625/2008030 ML20132C698
References
50-282-85-15, 50-306-85-12, NUDOCS 8509270126
Download: ML20132C712 (2)

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Appendix NOTICE OF VIOLATION Northern States Power Company Docket No. 50-282 Docket No. 50-306 As a result of the inspection conducted on June 25 - August 30, 1985, and in accordance with the General Policy and Procedures for NRC Enforcement Actions, (10 CFR Part 2, Appendix C), the following violations were identified: CFR 50, Appendix B, Criterion XVI, as implemented by Northern States Power Company Corporate Nuclear Administrative Control Directives, Section 10, requires conditions adverse to quality such as deficiencies, defective materials, and deviations be correcte In the case of a significant adverse condition, the cause of the condition shall be determined and corrective action taken to preclude repetitio Contrary to the above, after identifying a seal leak and fluid contamination in a steam generator snubber (SGS), the licensee did not investigate the cause of seal deterioration and fluid contaminatio In addition, the licensee did not perform tests on the other SGSs to assure operability and to identify the possible worst case condition (282/85015-01A and B; 306/85012-01A and B).

This is a Severity Level IV violation (Supplement II). CFR 50.73 requires the licensee to submit a Licensee Event Report (LER) within 30 days after discovery of condition that resulted in the nuclear power plant being seriously degraded, or that resulted in the nuclear power plant being in an unanalyzed condition that significantly compromised plant safety, or in a condition that was outside the design basis of the plan Contrary to the above, the licensee failed to submit LERs documenting (1) the identified seal leak and fluid contamination problem, (2) that the SGS control valves were replaced to avoid possible piping overstress, and (3) that a Westinghouse calculation indicated a SGS load significantly greater than the original design value (282/85015-02A, B and C; 306/85012-02A, B, and C).

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

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 8509270126 DR 850920 ADOCK 05000282 PDR

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Appendix 2 taken and the results achieved; (2) corrective action to be taken to avoid further violations; and (3) the date when full compliance will be achieve Consideration may be given to extending your response time for good cause show J gEp 2 019B,D k [/

Dated J. J. Harrison, Chief Engineering Branch t