TXX-6345, Forwards Rev 3 to S&W Procedure CPPP-7, Design Criteria for Pipe Stress & Pipe Supports
| ML20205M033 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/26/1987 |
| From: | Counsil W, Keeley G TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20205M036 | List: |
| References | |
| TXX-6345, NUDOCS 8704020252 | |
| Download: ML20205M033 (1) | |
Text
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March 26, 1987 Deswiw iice l' resident U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 and 50-446 TRANSMITTAL OF STONE & WEBSTER ENGINEERING CORPORATION PROCEDURE CPPP-7, REVISION 3 Gentlemen:
Enclosed are 15 copies of Stone & Webster Engineering Corporation's Comanche Peak Project Procedure CPPP-7, " Design Criteria for Pipe Stress and Pipe Supports," Revision 3.
A description of the changes made to CPPP-7 is located in the front of the procedure.
The Atomic Safety and Licensing Board will be notified of this transmittal per separate letter from our attorney.
Very truly yours, W. G. Counsil By:
G. S. Keeley Manager, Nuclear uy/j sing JDS/ef c-Mr. E. H. Johnson, Region IV Mr. D. L.oKelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV J