ML20108C858

Final Significant Deficiency Rept SD-60 Re Westinghouse Motors on Limitorque Motor Operated Valves.Initially Reported on 840927.Motors on Order for All Affected Valves. Motors Will Be Replaced Prior to Fuel Load

ML20108C858
Person / Time
Site:	Millstone
Issue date:	10/26/1984
From:	Counsil W NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
F0618A, F618A, SD-60, NUDOCS 8411190102
Download: ML20108C858 (2)

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s .o General Offices e Selden Street. Berlin. Connecticut l EsrY esaauama" nIaE== P.O. BOX 270 HARTFORD. CONNECTICUT 06141-0270 L L J [',*,", Z Z 7 "," ~. (203) 665-5000 October 26,1984 Docket No. 50-423 ,

F0618 A Dr. Thomas E. Murley Regional Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Dear Dr. Murley:

Millstone Nuclear Power Station, Unit No. 3 Reporting of Potential Significant Deficiencies in Design and Construction:

Westinghouse Motors on Limitorque Motor Operated Valves (SD-60)

In a September 27,1984 telephone conversation between your Mr. T. Rebelowski and our Mr. R. E. Lefebvre, Northeast Nuclear Energy Company (NNECO) reported a potential significant deficiency in the design and construction of Millstone Unit No. 3 as required by 10 CFR 50.55(e). The potential significant deficiency involves motors supplied by Westinghouse on Limitorque motor operated valves used in safety-related applications in the auxiliary charging pump miniflow line. We were notified by Westinghouse that motors on four Limitorque operators were not qualified to IEEE 323-1974 and IEEE 344-1975. A review determined that the valves were specified to these standards, however, no certification was supplied in the valve data package. Hence, we consider this to be a significant deficiency.

All of the subject valves are in the charging pump auxiliary miniflow line. Had this problem gone undetected, the valve may not have functioned to provide charging pump miniflow in the event of a steamline break or feedline break, which could ultimately have led to pump damage from running the pump without miniflow recirculation.

All affected valves have new, qualified motors on order. The unqualified motors willbe replaced with these new motors prior to fuelloading.

8411190102 841026 PDR ADOCK 05000423 S PDR

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- We consider this our final. report closing out SD-60. We' trust that the 'above information satisfactority responds to your concerns.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

. 25401

- W. G. Counsil Senior Vice President cc: Mr. R. C. DeYoung, Director Division of Inspection and Enforcement U. S. Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue Bethesda, MD 20014