ML20135E344

Notice of Violation from Insp on 961217-970127.Violation Noted:Licensee Identified That on 961216,auxiliary Operator Was Preparing Unit 2 Residual Heat Removal Sys for Fill & Vent Evolution & Did Not Open Valve 2RH-709A,as Required

ML20135E344
Person / Time
Site:	Point Beach
Issue date:	02/27/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20135E342	List: IR 05000266/1996019 ML20135E339 ML20135E344 ML20135E348
References
50-266-96-19, 50-301-96-19, NUDOCS 9703060442
Download: ML20135E344 (2)

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l NOTICE OF VIOLATION Wisconsin Electric Power Company Docket Nos. 50-266; 50-301;72-005 l Point Beach Nuclear Plar t License Nos. DPR 24; DPR-27 During an NRC inspection conducted from December 17,1996, through January 27, 1997, violations of NRC requirements were identified. In accordance with NUREG-1600, l

" General Statement of Pnlicy and Procedure for NRC Enforcement Actions," the violations  ;

are listed below: j l

1. 10 CFR 50,' Appendix B, Criterion V, " Instructions, Procedures, and Drawings," l requires, in part, that activities affecting quality be prescribed by documented instructions, procedure 1, or drawings, of a type appropriate to the circumstances and be accomplished in accordance with these instructions, procedures, or drawings.

Nucleai Power Department Procedure (NP) 5.3.1, Revision 4, " Condition Reporting System," identified items to be documented in e Condition Report (CR), including conditions that may affect equipment operability, and inadequate review of issues or resolution of problems.

A. Contrary to the above, the licensee identified that on December 16,1996, an auxiliary operator was preparing the Unit 2 residual heat removal system for a fill and vent evolution, an activity affecting quality, and did not open valve 2RH-709A, as required by a valve lineup list.

This is a Severity Level l'V violation (Supplement 1).

B. Contrary to the above:

a. The inspectors identified that on January 21,1997, a high fuel oil pressure alarm was received during a monthly test of the G-03 emergency diesel generator (EDG)--a condition that may affect EDG operability, and no CR was not written.

b. The inspectors identified that since October 23,1996, oil leaked from the P-35A electric fire pump motor during monthly tests--a condition that may affect motor operability, and no CR had been written.

This is a Severity Level IV violation (Supplement 1).

C. Contrary to the above, the inspectors identified that on November 26,1996, l a helicoil repair was performed on the Unit 2 "A" safety injection pump, an I

activity affecting quality, and appropriate instructions were not provided for accomplishing that repair, i

l This is a Severity Level IV violation (Supplement 1).

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l 9703060442 970227 i PDR ADOCK 05000266

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f Notice of Violation  !

2. Technical Specification (T/S) 15.4.2.B.3 requires, in part, that inservice testing l (IST) of American Society of Mechanical Engineers (ASME) Code Class 1,2, and 3  :

valves he performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code (1986) and applicable Addenda as required by 10 CFR EO.55a. i Saction IWV-3412(a) of Section XI, in part, requires that valves that cannot be exercised during plant operations be full-stroke exercised during cold shutdowns. j l Contrary to the above, the licensee identified that in the spring of 1995 and 1996, I Unit 1 was in cold shutdown for refueling outages and 1SI-852A, an ASME Code l

Class 2 valve that cannot be exercised during plant operations, was not full-stroke exercised. l l

This is a Severity Level IV violation (Supplement 1). l l

3. 10 CFR 50, Appendix B, Criterion XVI, requires, in part, that measures be established to assure that conditions adverse to quality be promptly identified and l corrected.

i Contrary to the above, the inspectors identified that from May 30,1991, to January 2,1997, the licensee was aware of the potential for a variation in the main steam safety valve setpoint due to ambient temperature changes--a condition

!. adverse to quality, but did not promptly correct this condition.

This is a Severity Level IV violation (Supplement 1).

Pursuant to the provisions of 10 CFR 2.201, Wisconsin Electric is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington. DC 20555, with a copy to the Regional Administrator, Region lil, and a copy to the NM Resident inspector, within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation, or if contested, the basis for disputing the violation; (2) corrective action taken and the results achieved; (3) corrective action to be taken to avoid further violations; and j (4) the date when full compliance will be achieved. Where good cause is shown, '

consideration may be given to extending your response time. ,

Dated at Lisle, Illinois this 27th day of February 1997

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