ML20050A922
| ML20050A922 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/29/1982 |
| From: | Parker W DUKE POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8204020401 | |
| Download: ML20050A922 (2) | |
Text
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Duxn Pownu CodiPm Powen 11 ult. DING 422 Sourn Cucacu STHEET, CnAHWTTE, N. C. e8242 March 29, 1982 WIL LI AM O. PA H pf E R, J R.
Vic t l'a t t+ Df g f TEL EpeeO p. g:Anga 704 Strase Paoovenog 373 4033 Q
E 4'
Mr. liarold R. Denton, Director Office of Nuclear Reactor Regulation 4
KI!CN i
APR 01gr' g U. S. Nuclear Regulatory Commission
[
Washington, D. C.
20555 m
..M.str 7 9-Attention:
Ms. E. G. Adensam, Chief gr.
Licensing Branch No. 4 4
g Re: McGuire Nuclear Station W
s Docket Nos. 50-369, 50-370
Dear Mr. Denton:
In accordance with NUREG 0737, Item 11.D.1, as revised by NRC letter on September 29, 1981, Duke Power Company submits the following information based on preliminary review of the safety and relief valve test results for McGuire Nuclear Station.
Duke Power Company has actively pursued resolution of this issue through direct participation in the Electric Power Research Institute (EPRI) valve test program.
The following reports prepared by EPRI are applicable to McGuire Nuclear Station and form the basis for this submittal.
a) Valve Selection Justification Report b) Test Condition Justification Report c) Valve Inlet Fluid Condition for Pressurizer Safety
& Relief Valves in Westinghouse Plants d) Safety and Relief Valve Test Report I
The above documents have been or will be transmitted to you by Mr. David Hoffman of Consumers Power Company on behalf of Duke Power and the other participating utilities on or before April 1, 1982.
Based on preliminary review of the above documents and the test results received to date, our review is summarized as follows:
RELIEF VALVE Manuf acture r Model Quantity Control Components, Inc.
3" Drag.
3 per unit These valves were tested by EPRI in a test configuration similar to an actual l
plant. The tests confirmed that the valves opened and closed, relieved overpressure, and suffered no damage that would preclude future operation.
8204020401 820329 h
PDR ADOCK 05000369 P
PDR gg g i
Harold R. Denton March 29, 1982 Page 2 SAFETY VALVE Manufacturer Model Quantity Crosby HB-BP-86, 6M6 3 per unit These valves were tested by EPRI in a test configuration similar to the actual McGuire plant arrangement. The valves were shown to open and close and to reduce overpressure. Several areas of potential concern were identified from preliminary test results and are being actively investigated.
Duke is currently investigating the above items for acceptability to McGuire Nuc1 car Station and will submit a formal report by July 1, 1982.
If it appears that the final report will be delayed beyond this date, a formal request for license amendment will be submitted since this date is specified in the McGuire Fac12it Operating License.
Very truly yours, e
s'
/
s N
C la. AA tb William O. Parker, Jr GAC/jfw cc:
Mr. P. R. Bemis Mr. James P. O'Reilly, Regional Administrator Senior Resident Inspector U. S. Nuclear Regulatory Commission McGuire Nuclear Station Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 I