ML14138A123
| ML14138A123 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/24/1983 |
| From: | Paulson W Office of Nuclear Reactor Regulation |
| To: | Dietch R Southern California Edison Co |
| References | |
| TASK-06-02.D, TASK-06-03, TASK-08-03.B, TASK-6-2.D, TASK-6-3, TASK-8-3.B, TASK-RR LSO5-83-02-047, LSO5-83-2-47, NUDOCS 8303010550 | |
| Download: ML14138A123 (1) | |
Text
February 24, 1983 Docket No. 50-206 LS05-83-02-047 Mr. R. Dietch, Vice President Nuclear 6ngineering and Operations Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770
Dear Mr. Dietch:
SUBJECT:
SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 -
SEP TOPICS VI-2.D, MASS AND ENERGY RELEASE FOR POSSIBLE PIPE BREAK INSIDE CONTAINMENT, VI-3, CONTAINMENT PRESSURE AND HEAT REMOVAL CAPABILITY, AND VIII-3.B, DC POWER SYSTEM BUS VOLTAGE MONITORING AND ANNUNCIATION By letter dated January 20, 1983 (R. Krieger to D. Crutchfield), you submitted comments on the above topics.
For the reasons discussed below, these topics are now considered to be final and any remaining differences from current criteria will be considered in the integrated assessment.
For Topics VI-2.D and VI-3, the revised calculations do not affect the staff conclusion of the adequacy of the containment heat removal capability. As noted in the staff's November 30, 1982 SER on Environ mental Qualification of Safety-Related Electrical Equipment, the staff has concluded that the LOCA temperature/pressure profiles are acceptable for that purpose. Therefore, the previous TER and SER, as transmitted in our letter of:January 12, 1982, are considered final.
For Topic VIII-3.B, the concerns expressed in our safety evaluation of July 24, 1981, still exist and will be addressed in the integrated assessment. The only change is that bus #1 voltage indication is provided; however, the staff position is that all dc buses should have voltage indication. Battery current and battery charger current indication should also be provided in the control room. The difference summary for this topic reflects this information.
Sincerely, Original signed by/
8303010556 930224
'Walter A. Paulson, Project Manager PDR ADOCK 05000206 Operating Reactors. Branch #5 P
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