ML20098G937
| ML20098G937 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Vogtle, Comanche Peak, 05000000 |
| Issue date: | 09/26/1984 |
| From: | Rahe E WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| REF-PT21-84-469-000 NS-EPR-2964, PT21-84-469, PT21-84-469-000, NUDOCS 8410090120 | |
| Download: ML20098G937 (2) | |
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' Westinghouse Water Reactor Nuclear TechnologyDivision Electric Corporation Divisions Boxass PittsburghPennsylvanials230 September 26, 1984 NS-EPR-2964 Mr. R. C.. DeYour g, Director Division of Inspection and Enforcement Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue Bethesda, Maryland 20014
Dear Mr. DeYoung:
This is to confirm the telephone conversation of September 26, 1984, between Messrs. C. G. Draughon and J. A. Achenbach of Westinghouse and Mr. Robi Singh of the NRC.
In that conversation Westinghouse notified the NRC of a reportable item associated with motors utilized in safety-related Limitorque operator applications. This item was reported under 10CFR50.55e for five construction plants ( A. W. Yogtle Units 1 and 2, Comanche Peak Units 1 and 2 and Millstone 'Jnit 3) as discussed below.
Westinghouse has advised these utility customers.-
Background and Description Westinghouse was informed by personnel at the lii11 stone 3 site that the motors on.four Limitorque operatcrs were not qualified to IEEE 323-1974 and IEEE 344-1975. A review of the purchase order determined that the valves were specified to those standards, but no certification was supplied in the valve data package. Westinghouse subsequently reviewed all other orders with the same requirements and determined that a similar problem exists on the A. W. Vogtle Units 1 and 2 and Comanche Peak Units 1 and 2 sites.
All affected 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 on the pump deadhead.
8410090120 840926 PDR ADOCK 05000424 PDR S
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Mr.-R. C. DeYoung September 26, 1984 NS-EPR-2964 Immediate Corrective Action Since no operating plants are involved, no immediate corrective action is required.
Pemanent Corrective Action All affected. motors have replacement, qualified units on order. All involved sites will have qualified motors installed prior to initial fuel loading.
If you yequire additional information on this subject, please contact J. A. Achenbach (412-374-4041) or C. G. Draughon (412-374-5761) of my staff.
Very truly yours, WESTINGHOUSE ELECTRIC CORPORATION E. P. Rahe, M., Manager Nuclear Safety Department CGD/anj
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