ML20057E817

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Notice of Violation from Insp on 930802-0903.Violation Noted:Controlling Work Document Did Not Provide Quantitative Acceptance Criteria for Establishing Leak Tightness of Boundary Valves
ML20057E817
Person / Time
Site: Point Beach  
Issue date: 10/06/1993
From: Forney W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20057E813 List:
References
50-266-93-12, 50-301-93-12, NUDOCS 9310130192
Download: ML20057E817 (2)


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NOTICE OF VIOLATION Wisconsin Electric Power Company Docket Nos. 50-266; 50-301 Point Beach Units 1 and 2 Licenses No. DPR-24; No. DPR-27 During an NRC inspection conducted August 2 through September 3, 1993, a

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violation of NRC requirements was identified.

In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violation is-listed below:

10 CFh 50, Appendix B, Criterion V, requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of. a type appropriate to the circumstances and shall be accomplished in accordanceL

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with these instructions, procedures, or drawings.. Instructions, procedures, l

or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.

Point Beach Nuclear Plant Procedure No' 3.4.21, " Voluntary Entry Into an LCO,"

i Revision 0, dated January 15, 1993, requires, in part, that contingency l

actions or plans that will mitigate the potential consequence of the equipment being unavailable shall be-part of the considerations for activities requiring entry into an LCO. Contingencies shall be addressed in the controlling work

-document.

Contrary to the above, when an LC0 was voluntarily entered on' July 13, 1993, to replace service water system valve No. SW-9 under work request No. 932809, the controlling work document did not provide:

a.

Quantitative acceptance criteria for establishing leak tightness of the boundary valves.

b.

Contingency actions to mitigate the potential consequence of having service water pumps A, B, and C unavailable.

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

Pursuarit to the provisions of 10 CFR 2.201, Wisconsin Electric Power Company is hereby required to submit a written statement'or explanation to the U.S.

Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C.

20555 with a copy to the Regional Administrator, Region III, and a copy to the NRC Resident Inspector at the Point Beach Nuclear Power Plant, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).

This reply should be clearly marked as a " Reply to' a Notice of Violation" and should include for the violation: (1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective' steps that i

will be taken to avoid further violations, and (4) the date when full compliance will be achieved.

9310130192 931006

'PDR ADOCK 05000266 G

PDR

Notice of Violation 2

If an adequate reply is not received within the time specified in this Notice, the Commission may issue an order or a demand for information 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. Where good cause is shown, consideration will be given to extending the response time.

s6 ay f ct be 93 b

William L. Forne.4Jcting Direct (or)

Division of Reactor Safety l

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