ML13333B722
| ML13333B722 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/09/1982 |
| From: | Paulson W Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8206240132 | |
| Download: ML13333B722 (2) | |
Text
Vk~
REG~4 UNITED STATES 0
NUCLEAR REGULATORY COMMISSION r
0 WASHINGTON, D. C. 20555 June 9, 1982 Docket No. 50-206 LICENSEE: Southern California Edison Company FACILITY: San Onofre Nuclear Generating Station, Unit No. 1
SUBJECT:
SUMMARY
OF MAY 14, 1982 MEETING On May 14, 1982, the NRC staff met with representatives of Southern California Edison Company. The purpose of the meeting was to discuss the licensee's response to the NRC's April 7, 1982 request for additional information regarding safe shutdown following a postulated steam line break. Enclosure 1 is a list of attendees. Copies of the viewgraphs and handouts used during the meeting are also enclosed (Enclosure 2).
The NRC staff has indicated concerns regarding the adequacy of the San Onofre Unit 1 emergency operating procedures for mitigating the effects of a postulated steam line break. The licensee indicated that they have reviewed the accident analyses with respect to necessary modifications to the procedures. The licensee is modifying the loss of coolant procedures; not just those related to a steam line break. The procedures are being modified using the Westinghouse emergency response guidelines. The differences between San Onofre Unit 1 and a standard plant are being considered in developing the guidelines. Some of the features at San Onofre Unit 1 are interconnected steam generators with no provision for individual steam generator isolation, low head - high capacity safety injection system, high head - low flow charging pumps, reactor coolant pumps trip on safety injection signal, and use of charging pumps to provide decay heat removal using feed and bleed. The avoidance of pressurized thermal shock was considered in the development of the revised procedures.
The licensee reviewed the work performed and provided a draft copy of the revised procedures. The procedures have not been approved by the station review committee as yet. At the request of the NRC staff, the licensee 560 indicated that they would recalculate the containment pressure response adding the feed-and-bleed mass and energy release for this mode of decay (a) heat removal.
Walter A. Paulson, Project Manager Operating Reactors Branch #5 Division of Operating Reactors
Enclosures:
As stated DESIGNATED ORIGINAL Certified By 8206240132 820609 PDR ADOCK 05000206 P
Mr. R. Dietch 2 -
June 9, 1982 cc Charles R. Kocher, Assistant General Counsel James Beoletto, Esquire Southern California Edison Company Post Office Box 800 Rosemead, California 91770 David R. Pigott Orrick, Herrington & Sutcliffe 600 Montgomery Street San Francisco, California 94111 Harry B. Stoehr San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector/San Onofre NPS c/o U. S. NRC P. 0. Box 4329 San Clemente, California 92672 Mayor City of San Clemente San Clemente, California 92672 Chairman Board of Supervisors County of San Diego San Diego, California 92101 California Department of Health ATTN:
Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814 U. S. Environmental Protection Agency Region IX Office ATTN:
Regional Radiation Representative 215 Freemont Street San Francisco, California 94111 Robert H. Engelken, Regional Administrator Nuclear Regulatory Commission, Region V 1450 Maria Lane Walnut Creek, California 94596