ML20125C676

Notice of Violation from Insp on 921005-29.Violations Noted: 10CFR50.59 Safety Evaluation for Temporary Alteration 90-053 Not Adequate to Provide Basis for Determination That Temporary Alteration Did Not Involve Unreviewed Question

ML20125C676
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	12/04/1992
From:	Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20125C660	List: ML20125C658 ML20125C676 ML20125C684
References
50-295-92-23, 50-304-92-23, NUDOCS 9212140032
Download: ML20125C676 (2)

Text

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NOTICE 01VI_O_LATION Commonweslth Edison Company Docket Nos. 50-295; 50-304 Zion Station Units 1 and 2 Licenses No. OPR-39; DPR-48 During an NRC inspection conducted on October 5 through 29, 1992, two violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violations are listed below:

1. 10 CFR 50.59 (b) (1) requires that records of changes made in the facility as described in the safety analysis report must include a written safety evaluation which provides the bases for the determination that the chango does not involve an unroviewed safety question.

Contrary to the above, the 10 CFR 50.59 safety evaluation for temporary alteration 90-053, " Bit Outlet Valve Leakage Rorouto To RCDT", dated June 9, 1990, was not adequate to provide a bcsia for the determination that this temporary alteration did not involve an unroviewed safety question.

This is a severity level IV violatice (9upplement I)

2. 10 CFR 50, Appendix B, Criterion XI, Test Control, states in part, that a test program shall be established to assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures.

Contrary to the above, on March 22, 1991, adequate testing required to demonstrate that components perform satisfactorily was not performed following maintenance on

valvo 1RH-8701. The maintenance work disabled a valve l interlock which was not verified by post-maintenance testing.

This is a Severity Level IV violation (Supplement I)

Pursuant to the provisions of 10 CFR 2.201, Commonwealth Edison Company is hereby required to submit a wiltten statement or explanation to the U.S. Nuclear Regulatory Commission, ATTH:

Document Control Desk, Washington D.C. 20555 with a copy to the U.S. Nuclear Regulatory Commission, Region III, 799 Roosevelt Road, Glen Ellyn, Illinois, 60137, and a copy to the NRC Resident Inspector at the Zion Station within 30 days of the date of the letter transmitting this Notice of Violation (Notice).

9212140032 921204 l PDR ADDCK 05000295 G PDR-

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Notico of Violation 2 This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violations (1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective stops that have been tnkon and the results achieved, (3) the correctivo stops that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. If an adequate reply is not received within the time specified in this Notico, an order or a domand for information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Whoro good cause is shewn, consideration will be given to extending the response time.

I Dated a Glen Ell , Illinois this d day of '

(twhM 1992  !!. JfjMiller, Director i Division of Heactor Safoty 3

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