ML20087C873

Potential Significant Deficiency Rept SD-51 Re Design & Const of Namco Model EA-180 Limit Switches Provided as Accessories on Valves Supplied by Pacific Valves.Initially Reported on 840131.Discussions W/Vendor Initiated

ML20087C873
Person / Time
Site:	Millstone
Issue date:	03/01/1984
From:	Counsil W, Sears C NORTHEAST UTILITIES
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
F0471A, SD-51, NUDOCS 8403130213
Download: ML20087C873 (2)

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HARTFORD. CONNECTICU. 06141-0270 (203)566-6911 March 1,1984 Docket No. 50-423 F0471A Dr. Thomas E. Murley Regional Administrator Region i U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Dear Dr. Murley:

i Millstone Nuclear Power Station, Unit No. 3 Reporting of Potential Significant Deficiencies in Design and Construction: NAMCO Model EA-180 Limit Switches (SD-51)

In a January 31, 1984 telephone conversation between your Mr. T. Rebelowski and our Mr. D. B. Vail, Northeast Nuclear Energy Company (NNECO) reported a potential significant deficiency in the construction of Millstone Unit No. 3 as required by 10CFR50.55(e). Subsequently, this was followed up with another telephone conversation with your Mr. T. Elsasser on February 1,1984.

The potential significant deficiency involves NAMCO Model EA-180 limit f switches provided as accessories on valves supplied by Pacific Valves. NAMCO l has determined that the splined lever shaf t in some NAMCO Model EA-180 limit l switches may not expand adequately to secure the operating lever when the expansion plug is tightened in the end of the shaft. A preliminary review performed by NUSCO Engineering has determined that this potential significant deficiency can adversely impact the operation of Category lE circuits and equipment.

The scope of impact of this significant deficiency upon Category IE circuits and equipment has not been determined at this time. Discussions with the vendor and an investigation of this deficiency have been initiated to define the scope of 8403130213 840301 PDR ADOCK 05000423 S PDR 6

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4 j impact and identify other possible affected Category IE equipment / circuits. We will provide you with an update on this matter as information becomes available.

Very truly yours, W . (v . bCit1A W. G. Counsii Senior Vice President 4

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g-1 By: C. F. Sears Vice President Nuclear and i Environmental Engineering cc: Mr. R. C. DeYoung, Director Division of Inspection and Enforcement U. S. Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue Bethesda, MD 20014 i

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