ML13333A493
| ML13333A493 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/29/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | James Drake Southern California Edison Co |
| References | |
| TASK-15-19, TASK-RR NUDOCS 8002140427 | |
| Download: ML13333A493 (5) | |
Text
DISTRIBUTION Docket NRC PDR Local PDR Docket No. 50-206 ORB Reading NRR READING DEisenhut RVollmer OELD Mr. James H. Drake OI&E (3)
JAN 2 9 198§ Vice President DLZiemann Southern California Edison Company PO'Connor 2244 Walnut Grove Avenue HSmith Post Office Box 800 NSIC Rosemead, California 91770 TERA ACRS (16)
Dear Mr. Drake:
DCrutchfield (2)
RE:
COMPLETION OF SEP TOPIC XV-19 Your letters dated April 9, 1979 and December 7, 1979, indicated that you have examined our draft evaluation of the subject topic dated [larch 15, 1979. You suggested editorial or corrective changes to the assessment to make it more accurately reflect your facility design.
We have incorporated your suggested modifi cations in the enclosed assessment.
With these modifications our review of the Radiological Consequences Portion of SEP Topic XV 19 is complete and will be a basic input to the integrated assessment of your facility.
The subject assessment compares your facility design with the criteria currently used by the staff in licensing new facilities. This assessment may need to be re-examined if you modify your facility or if the criteria are changed before we complete our integrated assessment.
Sincerely, Original Signed. by:
Dennis L. Ziemann Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors
Enclosure:
Completed SEP Topic XV-19 cc w/enclosure:
See next page DOR: ORB #2 DOR: -O.#2 DOR: ORB #2 O F F IC E SURNAME PO'Connor: cc H DLZiemann S
NRC FORM 318 (9-76) NRCM 0240
- U.S.
GOVERNMENT PRINTING OFFICE: 1979-289-369 January 29, 1980 cc Charles R. Kocher, Assistant Director, Technical Assessment General Counsel Division Southern California Edison Cocpany Office of Radiation Programs Post Office Box 800 (AW-459)
Rosemead, California 91770 U. S. Environmental Protection Agency.
David R. Pigott Crystal Nail 1 Samuel B. Casey Arlington, Virginia 20460 Chickering & Gregory Three Embarcadero Center U. S. Environnental Protection Twenty-Third Floor Agency San Francisco, California 94111 Region IX Office ATTN: EIS COORDINATOR Jack E. Thomas 215 Freemont Street Harry B. Stoehr San Francisco, California 94111 San Diego Gas & Electric Company P. 0. Box 1831 K M C, Inc.
San Diego, California 92112 ATTN:
Richard E. Schaffstall 1747 Pennsylvania Avenue, N. W.
Resident Inspector Suite 1050 c/o U. S. NRC Washington, D. C. 20006 P. 0. Box 3550 San Onofre, California 92672 Mission Viejo Branch Library 24851 Chrisanta Drive Mission Viejo, California 92676 Mayor City of San Clemente San Clemente, California 92672 Chai rman 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 9A3s4
San Onofre 1 Topic XV-19 Loss-of-Coolant Accidents Resulting from Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary - Radiological Consequences The safety objective of this review is to assure that the releases from this postulated event will not result in exposures in excess of the established guidelines.
An analysis of the radiological consequences of a postulated loss-of coolant accident (LOCA) was performed in support of Amendment No. 25 to the Provisional Operating License issued on April 1, 1977.
This analysis was performed following the assumptions and procedures indicated in the S.R.P. 15.6.5 and Regulatory Guide 1.4.
The doses obtained from this review were within the 10 CFR Part 100 guidelines as specified in the acceptance criteria for the S.R.P. 15.6.5 (Revision 0).
Presently we estimate the doses to be even lower in view of the less restrictive dispersion coefficients established in Topic II-2.C, "Atmospheric Dispersion". These doses, modified to reflect these updated X/Q values, are listed in Table XV-3. In addition, the total body doses calculated in 1977 included the contribution of both beta and gamma radiation, while current procedures consider only the effects of gamma radiation. As a result, the total body doses may be estimated to be about a factor of 2 lower.
On the basis of these results, we conclude that the radiological consequences of this postulated accident at the San Onofre Unit 1 plant are similar to those of plants licensed under current criteria.
References:
- 1. San Onofre Nuclear Generating Station Unit 1 - FSAR.
Section 13.1
- 2. Safety Evaluation by the Office of Nuclear Reactor Regulation Supporting Amendment No. 25 to Provisional Operating License No. DPR-13 for the San Onofre Nuclear Generating Station, Unit 1. April 1, 1977.
TABLE XV-3 ESTIMATED OFFSITE DOSES FOR POSTULATED LOSS-OF-COOLANT ACCIDENT Containment 0-2 Hour Leakage ECCS Leakage Exclusion Area Contribution*
Contribution Total Boundary Doses (REM)
(REM)
(REM)
Thyroid 129.6 26.4 156.0 Total Body 3.210 0.065 13.3**
Low Population Zone Doses Thyroid 0-8 hour 7.9 3.3 11.2 8-24 hour 2.7 2.0 4.7 24-96 hour 4.3 3.8 8.1 96-720 hour 42.5 3.3 45.8 Total 0-30 day 57.4 12.4 69.8 Total Body 0-8 hour 0.178 0.005 0.183 8-24 hour 0.043 0.003 j.046 24-96 hour 0.021 0.002 0.023 96-720 hour 0.092 0.001 0.093 Total 0-30 day 0.334 0.011
<1.4***
- Includes 45 cfm purge beginning 14.5 days after LOCA
- Includes 10 rem direct and skyshine dose from containment
- Includes <1 rem direct and skyshine dose from containment