ML13317B035
| ML13317B035 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/12/1982 |
| From: | Krieger R Southern California Edison Co |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| TASK-15-03, TASK-15-04, TASK-15-08, TASK-15-12, TASK-15-16, TASK-15-19, TASK-15-3, TASK-15-4, TASK-15-8, TASK-RR NUDOCS 8203170207 | |
| Download: ML13317B035 (2) | |
Text
Southern California Edison Company P.O. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 March 12, 1982 Director, Office of Nuclear Reactor Regulation Attention: D. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-206 Comments on Design Basis Event Reviews, SEP San Onofre Nuclear Generating Station Unit 1
References:
- 1. Letter, D. M. Crutchfield to R. Dietch, dated August 26, 1981, San Onofre 1 - SEP Topics XV-3, Loss of Load and XV-19, Loss of Coolant Accident (Systems).
- 2.
Letter, D. M. Crutchfield to R. Dietch, dated December 21, 1981, San Onofre 1 - Sep Topic XV-4 Loss of Non-Emergency A-C Power to Station Auxiliaries.
- 3. Letter, D. M. Crutchfield to R. Dietch, dated November 19, 1981, San Onofre 1 - SEP Topics XV-8 Control Rod Misoperation and XV-12 Spectrum of Control Rod Ejection Accidents.
- 4.
Letter, D. M. Crutchfield to R. Dietch, dated November 18, 1981, SEP Topic XV-16, Radiological Consequences of Failure of Small Lines Carrying Primary Coolant Outside Containment San Onofre 1.
Your referenced letters forwarded. completed topic assessments.
The letters requested a timely review of the assessments to verify the validity of the licensing bases and assumptions used relative to the as-built facility, San Onofre Unit 1.
The results of our reviews are enclosed.
If you have any questions regarding the enclosure, please let me know.
Si
- rely, R W. Kieger pervising Enginee an Onofre Unit 1 Li ensing Enclosure 1.8203170207 820312 PDR ADOCK 05000206 I
ENCLOSURE COMMENTS ON SEP TOPICS XV Topic XV-3, Loss of Load Topic XV-19, Loss of Coolant Accident (Systems)
The licensing bases assumed for these safety evaluation reports correctly reflect the characteristics of the as-built facility.
Topic XV-4, Loss of Non-Emergency AC Power to Station Auxiliaries The safety evaluation report on Topic XV-4 needs to list the reference:
- 2.
Letter from W. C. Moody, Southern California Edison Company, to Director, Office of Nuclear Reactor Regulation, NRC, Attention D. M. Crutchfield,
Subject:
Design Basis Event Review, SEP, San Onofre Nuclear Generating Station, Unit 1, dated July 1, 1981.
This reference supports the second and third paragraphs of Section V of the SER.
Topic XV-8, Control Rod Misoperation The licensing bases assumed correctly reflect the characteristics of the as-built facility.
Topic XV-12, Spectrum of Control Rod Ejection Accidents.
Topic XV-12 had an error in terminology and errors in fuel temperatures. The last sentence of the first paragraph on "Evaluation," should be:
"The maximum fuel clad temperatures ranged from 1305 0 F for the zero power, end of life case to 21090 F for the full power, beginning of life case; the maximum fuel temperatures (pellet centers) were 1792oF and 4491oF respectively and the average fuel temperatures (pellet) were 1580oF and 34020F.
Topic XV-16, Radiological Consequences of Failure of Small Lines Carrying Primary Coolant Outside Containment-San Onofre Unit 1 We feel that understanding of the "Evaluation" section of the SER on Topic XV-16 would be clarified by adding phrases thus:
"...We assumed that an iodine spike occurred...500-fold increase based on Technical Specifications concentrations in the iodine release...Section 15.6.2.
We assumed...environment was that contained in the maximum flashing fraction, 38%...."