TXX-4473, Deficiency Rept SDAR-170 Re Discrepancy Between Valve Weights Used in Stress Analysis Activities & Valve Weights Identified by Site Valve Weighing Program.Reanalysis Concluded Condition Not Reportable Under 10CFR50.55(e)
| ML20127M871 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/08/1985 |
| From: | Clements B TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | Hunter D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| SDAR-170, TXX-4473, NUDOCS 8505230375 | |
| Download: ML20127M871 (1) | |
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TEXAS UTILITIES GENERATING COMPANY NKYWAY TOWER. 400 NORTH OLIVE HTREET. L.B. 41. DALLAN TEXAM 15201 w ".'.So!,,"ffd'"L*,..
May 8, 1985 TXX-4473 Mr..D.R.-Hunter, Chief Reactor' Project Branch 2 U.S. Nuclear Regulatory Commission Office'of Inspection & Enforcement 611 Ryan Plaza Drive, Suite 1000 Docket Nos.: 50-445 Arlington, TX 76012 50-446 COMANCHE PEAK STEAM ELECTRIC STATION VALVE WEIGHTS QA FILE: CP-85-09, SDAR-170 FILE NO.:
10110
Dear Mr. Hunter:
On February 22, 1985 we verbally notified your Mr. J. Cummins of a deficiency between valve. weights used in stress analysis activities and the valve weights identified by the site valve weighing program. We have submitted interim reports logged TXX-4436 dated March 11, 1985 and TXX-4461 dated April 18, 1985.
' Selected stress problems which were determined to be " worst case" based on the percentage increase in valve weights were reanalyzed. This analysis included pipe stress, nozzle loading and valve acceleration. All results were within published specification allowables. Therefore, we have concluded that this condition,~if it had remained undetected, would not result in a condition adverse to safety and is not reportable under the provisions of 10CFR50.55(e).
Records supporting this determination are available for your inspector's review at the CPSES site.
Very truly yours, d
BRC:tig gggggT
-cc: NRC Region IV (0 + 1 copy)
NAY I O1985 Director, Inspection & Enforcement U.S. Nuclear Regulatory Commission
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