ML13310A699
| ML13310A699 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/10/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Dietch R Southern California Edison Co |
| References | |
| TASK-15-07, TASK-15-7, TASK-RR LSO5-82-02-056, LSO5-82-2-56, NUDOCS 8202180337 | |
| Download: ML13310A699 (3) | |
Text
February 10, 1982 Docket No. 50-206 LS05 02-056 Mr. R. Dietch, Vice President Nuclear Engineering and Operations Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770
Dear Mr. Dietch:
SUBJECT:
SAN ONOFRE 1 - SEP TOPIC XV-7, LOCKED REACTOR COOLANT PUMP ANALYSIS - REQUEST FOR ADDITIONAL INFORMATION We have reviewed the topic assessment on the above topic that you submitted on July 1,-1981, and we find that additional information is needed to com plete our safety evaluation.
Please provide the requested information within 30 days of receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, 0MB clearance is not required under P.L.96-511.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 1/
Division of Licensing
Enclosure:
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.sI6f Request for Additional Information E
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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-35-960
Mr. R. Dietch 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 Mission Viejo Branch Library 24851 Chrisanta Drive Mission Viejo, California 92676 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
ENCLOSURE SAN ONOFRE SEP TOPIC XV-7 REQUEST FOR ADDITIONAL INFORMATION An analysis comparing the RCP rotor seizure accident with the RCP shaft break is requested to identify the limiting case with respect to maximum RCS pressure and limiting fuel performance. The analyses of these events presented in your topic assessment which utilized a comparison to the Surry Nuclear Plant's analyses are not sufficient to determine if the DNBR limits are met. Your analysis should assume a loss of off site power as a result of turbine trip, the Technical Specification limit of steam generator tube leakage and a single active failure in safety systems. Appropriate delay time for loss of offsite power may be assumed if suitably justified. The evaluation should include tabula tions of the sequence of events, disposition of normally operating systems, utilization of safety systems and transient curves including RCS pressure and DNBR and reactor coolant flow for the limiting accident.
Confirm that the results of the analysis meet the acceptance criteria for these events per.SRP 15.3.3. Assume any fuel rod which has a DNBR less than the minimum allowable value for San Onofre fails. State the amount of failed fuel in the results of the analysis.