ML20084E749
| ML20084E749 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/18/1972 |
| From: | Koprowski R ROCHESTER GAS & ELECTRIC CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20084E695 | List: |
| References | |
| NUDOCS 8304150334 | |
| Download: ML20084E749 (2) | |
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K0CHESTER CAS At4D ELECTRIC CORPORATION e 69 EAST AVENUE, ROCHESTER, fl.Y.14LO4
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... -,,, s a s.: ice August 18, 1972 Mr. James P. O'Reilly, Director U. S. Atomic Energy Commission Region 1 Directorate of Regulatory Operations 970 Broad Street Newark, New Jersey 07102 Re: Docket No. 50-244
Dear Mr. O'Reilly:
This is in reply to your letter of June 22, 1972 requesting information on valve wall thicknesses. At the time valves for our plant were purchased, the applicabic codes and standards did not require documentation of valve wall thicknesses. We therefore have no verification records available to demonstrate acceptable l
wall thicknesses on valves important to nuc1 car safety.
Conducting a program to demonstrate acceptable wall thick-nesses on all valves important to nuclear safety in an operating plant is a significant undertaking. Due to the substantial radiation exposure involved, the limited numbers of personnel available to the industry for performing the required testing, and the nr ture of the problem, we do not feel that it warrants such a commitment.
The only problems of which we are aware in the industry in-volve cast body valves. Since different processes are used in the manufacture of forged body valves and the integrity of those installed in our plant has been successfully demonstrated by hydrostatic testing, we intend to limit our program to cast body valves.
8304150334 730615 PDR ADOCK 05000244 P
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f noCtri.5TER G AS AND CLEC TRIC CORP SHEET NO.
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August 18, 1972 70 Mr. James P. O'R, y Due to the reported problems with cast body valves, we pro-pose to measure the wall thickness of one (1) valve of each size of each manufacturer of all cast body valves important to nuclear safety installed at our plant. If any valves are found to have wall thick-nesses under those specified, action will be taken to verify the adequacy of the measured wall thickness or make repairs and con-duct additional inspection of similar valves. Our present schedule for refueling shutdowns and the lack of readily availabic procedures and equipment to perform the measurements will result in this program requiring five (5) years for completion.
Very truly yours,
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R. R. Koprowski Vice President and Chief Engineer l
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