ML13333A332
| ML13333A332 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/07/1978 |
| From: | Haynes J Southern California Edison Co |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7812200132 | |
| Download: ML13333A332 (3) | |
Text
Southern California Edison Company P. 0.
BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 December 7, 1978 Director of Nuclear Reactor Regulation Attention: Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Systematic Evaluation Program San Onofre Nuclear Generating Station Unit 1 Your letter of October 29, 1978 forwarded completed topic assessments for two SEP topics. That letter requested that we examine the facts upon which the staff based its evaluation and respond either by confirming that the facts defining San Onofre Unit 1 are correct or by identifying any errors.
The results of our examination of the facts defining San Onofre Unit 1 in each topic assessment are provided as an enclosure to this letter.
If you have any questions regarding the enclosed, please contact me.
Very tru
- yours, J. G. Haynes hief of Nuclear Engineering Enclosure REGULAI" I[0iZT TI;O 7Si2OO 0#0
Mr. D. L. Ziemann, Chief December 7., 1978 bec: 0. J. Ortega/J. H. Drake
,K. P. Baskin H. B. Ray D. N. Barry/J. A. Beoletto H. L. Ottoson J. M. Curran D. E. Nunn W. C. Moody J. C. Sorensen C. A.
Carossino E.
J. Donovan J. L. Rainsberry NRC Files NE Files R. E. Schaffstall (KMC, Inc. -
SEP Owners Group)
J. Harris (SDG&E)
Date: 2 j_____I ORGAN ' Initials i Mgr, EDO Mgi, GES CiSet, NucL Eny. Affairs Tech. Orgs.
RESULTS OF SCE EXA1INATION OF FACTS DEFINING SAN ONOFRE UNIT 1 IN NRC TOPIC ASSESSMENTS XV-17 Radiological Consequences of Steam Generator Tube Failure (PWR)
Table XV-1, Item 8, lists the exclusion area boundary as 284 meters.
The value which was reported in our Amendment 52, and which was used by the NRC Staff in their Amendment 25 to the Unit 1 Provisional Operating License, is 283 meters.
Table XV-1 includes a footnote which states: "The 0-2 hr X/Q for ground release is 9.5 x 10-4 sec/m 3 based on the site meteorological data."
The results of SCE's tracer studies justifying site X/Q's have been reported in detail to the NRC in several letters and meetings.
In Amendment 37 to the Unit 1 Provisional Operating License, and in Table XV-1 of this topic assessment, the NRC has indicated that a X/Q of 9.5 x 10-4 sec/m 3.was appropriate. SCE has not previously been informed of this value, the method of determining it, or the appropriateness of using this value in future dose calculations.
Table XV-2 lists accident doses at nearest site boundary. It is noted that this table is similar to Table 2.1 included in the NRC's Amendment 25 to the Unit 1 Provisional Operating License. However, Table 2.1 lists all values less than 1 simply as "<1".
Since the values in Table XV-2 are NRC calculations, SCE cannot verify their accuracy.
XV-18 Radiological Consequences of Main Steam Line Failure Outside Containment See comments on Topic XV-17 above.