ML18153D293
| ML18153D293 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 04/08/1993 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 93-034, 93-34, IEB-79-14, NUDOCS 9304150049 | |
| Download: ML18153D293 (2) | |
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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 8, 1993 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 Serial No.
NL&P/ETS Docket Nos.
License Nos.
COMPUTER PROGRAMS FOR PIPE STRESS ANALYSIS93-034 50-280 50-281 DPR-32 DPR-37 Surry Units 1 and 2 used the NUPIPE computer code to complete the reanalysis of safety-related piping pursuant to NRC Bulletin 79-14. Use of the NUPIPE computer code for pipe stress analysis was approved for Units 1 and 2 in NRC Safety Evaluation Reports, dated August 22, 1979 and March 26, 1980, respectively. Since that time, the NUPIPE computer code has been used as the analysis of record for all safety-related piping analysis.
With the recent advancement in the capabilities of personal computers (PC),
numerous PC-based pipe stress analysis programs are available as alternatives to main-frame computation using NUPIPE. These alternatives provide greater flexibility and an enhanced response capability for engineering to
- support operational requirements. In addition, pipe stress analysis is considerably less expensive when performed with a PC-based program. Therefore pursuant to 1 O CFR 50.59, Virginia Electric and Power Company intends to use PC-based pipe stress analysis programs for future modifications or reanalysis of safety-related piping systems at Surry Units 1 and 2.
Prior to using any computer program other than NU PIPE as the analysis of record, the program will be verified in accordance with our software control program. In addition, a safety evaluation will be performed for each new computer code to be used. The UFSAR will be revised accordingly to reflect the use and acceptability of each new computer pipe stress analysis program.
Very truly yours, Jl C~--'---*-
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W. L. Stewart Senior Vice President - Nuclear 049. 930408
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cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station