ML13330B195
| ML13330B195 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/15/1987 |
| From: | Medford M Southern California Edison Co |
| To: | NRC Office of Administration & Resources Management (ARM) |
| References | |
| NUDOCS 8704220304 | |
| Download: ML13330B195 (2) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 M.O.MEDFORD TELEPHONE MANAGER OF NUCLEAR ENGINEERING (818) 302-1749 AND LICENSING April 15, 1987 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-206 Progress on Selected Regulatory Projects San Onofre Nuclear Generating Station Unit 1
Reference:
Letter, M. 0. Medford, SCE, to Document Control Desk, NRC, dated March 16, 1987 Enclosed with this letter is the 18th edition of our description of the progress on selected regulatory projects now ongoing for San Onofre Unit 1. As was indicated in the previous edition (see reference), there does not appear to be a continuing need for these monthly reports.
If there are any questions on these projects, please contact me.
Very truly yours, Enclosure cc:
R. F. Dudley, NRR Project Manager, San Onofre Unit 1 J. B. Martin, Regional Administrator, NRC Region V F. R. Huey, NRC Senior-Resident Inspector, San Onofre Units 1, 2 and 3 8704220304 870415 PDR ADOCK 05000206 R
Enclosure PROGRESS ON SELECTED REGULATORY PROJECTS SAN ONOFRE UNIT 1 EDITION 18 Introduction The following is the 18th edition of the progress* on selected regulatory projects at San Onofre Unit 1.
Third Train of Auxiliary Feedwater There has been no change in the status of this item.
TDI Diesel Generators SCE submitted a letter on March 25, 1987,.which concludes that adding modified automatic slow start capability to the TOI diesel generators is adequate to achieve the long term safety objectives relative to NRC concerns related to the crankshaft. The letter also committed to providing Technical Specifications for slow surveillance starts at the time the preliminary design and engineering for the modification have been completed.
Control Room Habitability There has been no change in the status of this item.
Supplement 1 to NUREG-0737 As part of the resolution of the issues associated with this item, the Design Criteria for a Safety Parameter Display System (SPDS) at San Onofre Unit 1 were transmitted to the NRC by letter dated March 17, 1987.
The next action associated with this item will be the submittal of the final report of the Control Room Design Review by August 14, 1987.
Inadequate Core Cooling There has been no change in the status of this item.
Reactor Trips Experienced in Last Twelve Months In the last twelve months there have been three reactor trips. They occurred on July 17, 1986; August 5, 1986 and March 10, 1987.
Previous Month's Plant Availability The Availability of San Onofre Unit 1 for the month of March 1987 was 90.67%.
Progress represents the submittal of information to the NRC, completion of a modification with a regulatory due date, meetings or site visits by the NRC staff or their contractors.
Internal actions by SCE or the NRC staff continue on each item but are not reported in this document.
GEH:5077F