ML20151L375
| ML20151L375 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 07/28/1988 |
| From: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GO1-88-0056, GO1-88-56, NUDOCS 8808040022 | |
| Download: ML20151L375 (2) | |
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WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968
- 3000 George Washington Way
- Richland. Washington 99352 Docket No. 50-460 July 28, 1988 G01-38-0056 Document Control Desk U. S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C.
20555
Subject:
NUCLEAR PROJECT NO. 1 MECHANISTIC FAILURES IN THE MIN STEAM AND FEEDWATER ISOLATION AREA
References:
- 1) Letter, Lester S. Rubenstein (USNRC) to D.W. Mazur (Supply System), "WPPSS Nuclear Project 1 - Mechanistic Failures in the Main Steam and Feedwater Isolation Area," (GIl-88-0055), dated April 21, 1988.
- 2) Letter, G.C. Sorensen (Supply System) to J.F.
Stolz (USNRC), "Nuclear Project No. 1, Non-Mechanistic Failures in main Steam and Feedwater Isolation Area," (G01-86-0135), dated October 1, 1986.
We have received the NRC evaluation of our request for application of an alternate requiremtnt for qualification of the Main Steam and Feedwater Isolation Area. For your information at construction restart, we plan to dugment our previous submittal to more clearly indicate that:
a) the MSFIA structure with the planned modt fications can withstand the effects of "Non-Mechanistic" piping failure in a six inch diameter modulating steam dump line and b) the environmental qualification of essential equipment in i.he MSFIA will conform to the requirements of BTP ASB 3-1.
Following Construction restart, we expect to hold a d(stgn review meeting with the NRC to address this matter.
Key topics for discussion during the design review meeting will be:
Proposed changes to plant design based on the extensive study of the effects arising from postulated piping failures.
Basis for the postulation of the "mechanistic" circumferential pipe break in four inch diameter steam line.
Design capability (with the proposed modifications) to withstand the effects of postulated non-mechanistic pipe break in the six inch diameter modulating steam dump line.
Conformance of the environmental qualificatian of essentia? equipment in
%ggl the MSFIA to the requirements of BTP ASB 3-1.
Superior piping design features in the MSFIA.
I O 8808040022 880728 PDR ADOCK 05000460 A
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NRC Letter Page 2 a
When construction resumes we will develop a schedule for resolution of all open
..i tems related to non-mechanistic failures in the main steam and feedwater
' isolation area.
Following the design review meeting with the NRC and the augmented technical submittal the applicable revisions will be incorporated in the FSAR.
f Should you have 'any questions, please contact Mr. D. W. Coleman, WNP-1 Licensing Manager.
,2
.h G. C. Sorensen,' n'ager Regulatory Programs-(280)
GCS/GKD/llw cc:
J.B. Martin / NRC Region V G.S. Vissing/ NRC L.S. Rubenstein/ NRC N.S. Reynolds/ BCP8R D. Smithpeter/ BPA J.R. Lewis / BPA
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