ML13317B103
| ML13317B103 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/20/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Dietch R Southern California Edison Co |
| References | |
| LSO5-82-04-053, LSO5-82-4-53, NUDOCS 8204260084 | |
| Download: ML13317B103 (3) | |
Text
April 20, 1982 Docket No.
50-206 LSO5-82-04-053 00 C
Mr. R. Dietch, Vice President Nuclear Engippeering and Operations Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770
Dear Mr. Dietch:
SUBJECT:
STEAM LINE BREAK ACCIDENT, REQUEST FOR ADDITIONAL INFORMATION SAN ONO-IfRE NUCLEAR GENERATING STATION UNIT 1
Reference:
Letter from K.P. Baskin to D. M. Crutchfield, "Auxiliary Feedwater System Review," dated February 2, 1982.
As part of the Systematic Evaluation Program refiew of the effects of steam line breaks inside and outside containment at San Onofre Unitil, a concern was raised by the staff about the consequences of injecting cold auxiliary feedwater into a hot, dry steam generator following a steam line or feed water line break. The staff determined that additional information was necessary before the review of these topics could be comPleted. The refer enced letter was Southern California Edison's response to our request for additional information.
In Enclosure 1 of the referenced letter it was stated that "Westinghouse's best estimate judgment is that injection of cold AFW into a hot, dry steam generator can occur at a flow rate not exceeding 800 gpm without brittle ftacture or ductile fatigue rupture ofthbepMnay pressure boundary or the secondary shell." In a telephone conference with your staff, we determined that Westinghouse had not done an actual analysis of the accident conditions to reach their best estimateJudgment. Therefore, the technical bases used in reaching the conclusions in Enclosure 1 of the referenced letter are not adequate.
We request that you provide sufficient technical bases, such as a fractufe mechanics analysis, to support your conclusion that the integrity of the steam generators will not be affected liiythe addition of cold auxiliary feed water. Provide your response within 30 days of the receipt of this letter so that our evaluation can be completed in a timalamanner.
e 8204260 0 SURNAME SURNAME NRC FORM 318 (10-80) NRCM 0240 OFF ICIAL RECORD COPY USGPO: 1981-335-960
-2 The reporting and/or recordkeeping req flrements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Divisdon of Licensing cc:
K. Kniel W. Hazelton R. Klecker R. Hermann E. McKenna
- 1. Y. Chen G. Cwalina M. Boyle MTEB R. K cker 4/
82 Ah OFFICE.
- DL SURNAME y b GC na WRussell WPaulson.
DCr Whfie s
DATE
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4/82 418 /82 4*4/
2 NRC FORM 318 (10-80) NRCM 0240 OFFICIAL R ECORD COPY USGPO* 1981-335-960
DocKet No.
DU-4UD Revised 3/30/82
_t4lr'. 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 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