ML20071B338
| ML20071B338 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/11/1983 |
| From: | Tucker H DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-83 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8302280170 | |
| Download: ML20071B338 (2) | |
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.g DuxE POWER GOMPANY P.O. BOX 33809 CHARLOTTE, N.C. 28949 IlAL B. TUCKER reternows
'vna emmeenswt (704) 373-4538 February 11, 1983 w
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Mr. James'P. O'Reilly, Regional Administrator-Q d.
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U. S. Nuclear Regulatory Commission m
3 Region II T
j fj 101 Marietta Street, Suite 3100 f
3 Atlanta, Georgia 30303 ua F
Re: Catawba Nuclear Station en
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Units 1 and 2 re gW Docket Nos. 50-413 and 50-414 i
Dear Mr. O'Reilly:
Pursuant to 10 CFR 50.55e, please find attached Significant Deficiency Report CD 413-414/83-01.
1 Very truly yours, 0 4Vk Hal B. Tucker RWO/php Attachment ec: Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. P. K. Van Doorn NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq.
Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance i
2135 Devine Street Columbia, Soath Carolina 29205 EOFFICIAL COPY
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8302280170 830211 PDR ADOCK 05000413 S
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.g Duke Power Company Catawba Nuclear Station Report Number: SD 413-414/83-01 Report Date: February 11, 1983 Facility: Catawba Nuclear Station, Units 1 and 2
' Identification of Deficiency: Certain valve electric operator mounting plates are undersized. This deficiency was identified December 21, 1982. The NRC was notified by the valve manuf acturer per 10 CFR Part 21 by a letter dated January 7,1983.
Initial Report: On January 12, 1983, V. Brownlee, NRC Region II, Atlanta, Georgia was notified of the subject deficiency by W. O. Henry, J. K. Berry, and M. Childers of Duke Power Company, Charlotte, North Carolina 28242.
Component and Supplier: Duke Item 2B-378. Valve tags 1CA178, 1RN839A, 1RN841B,..RN839A, 2RN841B. The valve is an active 8-inch, 150 pound, ASME Section III, Class 3 wafer butterfly valve with a Limitorque SMB-000-2/H0BC electric actuator / gear reducer.
The valve serial numbers are N68159-1 and N53652-1 through 5.
There are a total of six installed valves affected by this deficiency.
The valve supplier is BIF-A Unit of General Signal, 1600 Division Road, West Warwich, Rhode Island 02893.
Description of Deficiency: An electric operator mounting plate on a BIF valve, Duke Item 2B-378 would be overstressed during a seismic event. This deficiency was discovered by BIF during a review of their seismic report (BIF report No.
N53653, Duke No. CNM-1205.02-0236). The mounting plate on the installed valve is designed for a manually operated valve and is 7/16 inch thick. An electrically operated valve requires a thicker mounting plate. The seismic report references a thicker plate'(0.60 inch).
Analysis of Safety Implications: Overstressing the actuator mounting plate during a seisaic event could preclude the valve from performing its intended safety related function. Valves 1,2RN839A and 1,2RN841B isolate the "Non-essential" Heat Exchanger header section of the RN System. These valves are normally open but receive a Safety Injection signal to close, thereby shedding non-essential header component loads.
Corrective Action: BIF will provide labor and materials to correct the problem.
A qualified, thicker (3/4 inch) actuator support plate will be provided. BIF will revise seismic reports and outline drawings as necessary. Valve modifica-tions will be completed by July 1, 1983. McGuire and Oconee Nuclear Stations BIF valve applications were reviewed to determine if a similar deficiency existed.
No such deficiencies were identified.
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