ML19282B802
| ML19282B802 | |
| Person / Time | |
|---|---|
| Issue date: | 02/28/1979 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Anderson T WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| Shared Package | |
| ML19282B803 | List: |
| References | |
| NUDOCS 7903160205 | |
| Download: ML19282B802 (2) | |
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.g WASHINGTON D. C. 20555 NUCLEAR REGULATORY COMMisslON 7
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t FEB 2 81gp-Mr. Thomas M. Anderson, Manager Nuclear Safety Department Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230
Dear Mr. Anderson:
SUBJECT:
SAFETY EVALUATION AP-8904 The Nuclear Regulatory Commission has completed its review of Westinghouse Electric Corporation Topical Report WCAP-8904 (Non-proprietary) entitled
" Westinghouse Emergency Core Cooling Evaluation Model for Analyzing (N-1)
Loop Operation of Plants With Loop Isolation Valves".
Our safety evalua-tion is enclosed.
As a result of our review of WCAP-8904, we have determined that the evalua-tion model described therein is conditionally acceptable for loss-of-coolant accident analyses for large and intermediate sized breaks of Westinghouse 3-loop and 4-loop reactors that are operated with one reactor coolant loop isolated.
The conditions of acceptance are (1) that at least two nodes are used for the postulated inactive loop break and (2) that momentum flux is accounted for by the methods described in WCAP-8341 (Proprietary) and WCAP-8342 (Non-proprietary) entitled " Westinghouse Emergency Core Cooling Evaluation Model - Sensitivity Studies".
Accordingly, topical report WCAP-8904 is acceptable for reference in license applications.
Each license application that references the methods of WCAP-8904 must provide results of analyses for a postulated active loop break and an inactive loop break to assure that the postulated break location resulting in the maximum fuel cladding temperature has been considered.
In accordance with established procedure, it is requested that Westinghouse issue a revised version of this report within three months of receipt of this letter to include the NRC acceptance letter, the enclosed evaluation, and any changes resulting from the review.
We do not intend to repeat our review of this report when it appears as a reference in a particular license application except to assure that the material presented in this report is applicable to the specific plant
, involved.
79031602o5
Mr. Thomas M. Anderson FEB 2 8 GI3 Should tiuclear Regulatory Commission criteria or regulations change, such that our conclusions concerning this report are invalidated, you will be notified and given an opportunity to revise and resubmit your +.opical report, should you so desire.
Sincerely, IJohn F. Stolz, Chief (Lfght Water Reactors Branch flo.1 Division of Project Management
Enclosure:
Safety Evaluation cc: Mr. Dave Rawlins Westinghouse Electric Corperation P. O. Box 355 Pittsburgh, Pennsylvania 15230
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