ML20073T008
| ML20073T008 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/09/1983 |
| From: | Horin W DEBEVOISE & LIBERMAN, TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | Stucky S NRC OFFICE OF THE SECRETARY (SECY) |
| References | |
| NUDOCS 8305100267 | |
| Download: ML20073T008 (5) | |
Text
{{#Wiki_filter:% LAW OFFICES OF DEBEVOIS E & LIBERMAN 8200 SEVENTEENTH STREET. N W l WASHINGTQ 0.c. 2 OO3 e y / T ELEPHONE (2 0'21851-9800 ,f' (.c' ep \\4 y ~. May 9, 1983 ,J i^ -{ n g_ o t I..a b:y ,a \\ Q e:c /~ : N}/h ~N; 'd2 Mr. Scott W. Stucky h / Office of the Secretary U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Docketing and Service Branch Re: Texas Utilities Generating Co., et al. (Comanche Peak Steam Electric Stations, Units 1 and 2): Docket Nos. 50-445 and 50-446
Dear Mr. Stucky:
Enclosed are the original signature pages to the affidavits of Messrs. Marshall, Wade, Finneran and Woodlan filed by Applicants in this proceeding on May 5, 1983. As noted thereon, the signature pages accompanying the affidavits when filed were telecopy facsimiles and the originals were to be transmitted under separate cover. Sincerely, /.~ William A. Horin Counsel for Applicants cc: Service List i O B305100267 830509 PDR ADOCK 05000445 0 PDR
s . safety-related but for which some degree of quality assurance was applied during design and construction. These items are those which augment the reliable performance of safety-related items or which reduce risk to the health and safety of the public but which are not classified as Safety Class 1, 2 and 3, Seismic Category I or Class lE. FSAR 517A.1. In sum, 10 C.F.R. Part 50, Appendix B requirements are not imposed simply on the systems or components which are safety-related, but on other items in accordance with their importance to safety, as contemplated by the Denton memorandum. A s fad < Marsfall John S. County of Dallas ) ) State of Texas ) Subscribed and sworn to before me this 5th day of May, 1983. k Notary Public G Lt... a. in cnd fer c.:.2.....77-8, A- ... 4 14 Ccmmission np;rv s Shutdown Panel ("HSP") had been completed but the test report had not been issued. That report has now been completed and is attached hereto. */ The objective of the test was to qualify the welding of the HSP and, by virtue of structural similarity the welding of the main control board panels. The report indicates that this objective has been achieved. As indicated in the report, "no weld-related f ailures or problems occurred during the tests." Thus, the report concludes that the panels furnished by Reliance Electric Company for Comanche Peak are structurally sound and suitable for their intended use, and that they do not compromise the performance or safety of the plant in any manner, rN 9f _ \\ / Q11 A D - 4lJ David H.~ Wade County of Somervell ) State of Texas ) Subscribed and sworn to before me this 5th day of May 1983. /0xs W Y d.c w^ 9 Notary Public U
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The Board had requested that this report be provided when completed. April 7, 1983, Conference Call, Tr. 22-23 O Comanche Peak. Specifically, Westinghouse will consider the clamp pre-load stresses in the pipe and pipe-to-clamp load transfer stresses. Westinghouse expects to complete its analysis of these i stresses in the near future. To date, the analysis has not disclosed any violation of applicable Code requirements for the analyzed stresses. If the analysis determines that any applicable ASME Code requirements are not met, Applicants will take appropriate corrective action. The analysis of these clamps will be subject to NRC review and corrective action (if any) will be subject to NRC approval. f n f . phnC. Finneran, Jr. j County of Somervell) State of Texas ) Subscribed and sworn to before me this 5th day of May 1983. bki M d os - ~ Notary Publie> l l i l I f i --.,---,.,n
4 i i t _7_ 4' reactor protection system for Comanche Peak, which began construction in 1974, has always satisfied IEEE-279 requirements. l VI. Conclusion In conclusion, the reactor protection system at Comanche Peak, including the reactor trip breakers, has been designed to satisfy all applicable NRC requirements. In addition, the reactor protection system for Comanche Peak meets IEEE-279 requirements, and Westinghouse has demonstrated that additional diversity in the reactor trip breakers need not be implemented for Westinghouse facilities. \\ l Donald R. Woodlan County of Dallas ) ) State of Texas ) Subscribed and sworn to before me this 5th* day of May, 1983. Notary Public GLENDA CEO,.. In and fcr Csa: Oct:r. ics:- FG Cer. mission Expira-2 I7-85" .}}