ML13324A809
| ML13324A809 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/07/1986 |
| From: | Medford M Southern California Edison Co |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8603110229 | |
| Download: ML13324A809 (3) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 M.O.MEDFORD TELEPHONE MANAGER, NUCLEAR LICENSING (818) 302-1749 March 7, 1986 Director, Office of Nuclear Reactor Regulation Attention:
Mr. G. E. Lear, Director PWR Project Directorate No. 1 U. S. Nuclear Regulatory Commission 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 G. E. Lear, NRC, dated January 29, 1986 Enclosed with this letter is the fifth revision of our description of the progress on selected regulatory projects now ongoing for San Onofre Unit 1. The previous description of this status was submitted via the reference. We will continue to provide monthly updates of the enclosure for your information.
If there are any questions on these projects, please contact me.
Very truly yours, Enclosure 7
603110229 B603f 1~
PDR ADOCK 05000206 R
Enclosure PROGRESS ON SELECTED REGULATORY.PROJECTS SAN ONOFRE UNIT 1 REVISION 5 Introduction The following is Revision 5 of the progress on selected regulatory projects at San Onofre Unit 1.
Long-Term Service Seismic Upgrading Most of the NRC concerns regarding criteria and methodology for the program have been resolved. SCE is currently reevaluating its methodology for evaluation of structural steel members and the potential impact of this on the outage. This will be discussed with the NRC, following SCE's review. Audits and meetings were conducted by the NRC staff and their consultants during the week of February 17 - 22, 1986. Additional system audits will be conducted during the week of March 18 - 21, 1986 and a site inspection will be conducted during the week of April 14, 1986.
Modifications required to upgrade systems and equipment will be completed during the current outage.
Fire Protection A site visit by the new NRC systems reviewer on fire protection was conducted on February 7, 1986. The purpose of the meeting was to review the system safe shutdown related aspects of SCE's submittals to demonstrate compliance with Section III.G of Appendix R to 10CFR50. A walk down of related plant areas was conducted.
SCE's fire protection modifications continue to be scheduled for completion prior to restart from the current outage.
Environmental Qualification During the current outage SCE is completing the replacement/upgrade of equipment for the Environmental Qualification Program. This work continues on schedule.
Third Train of Auxiliary Feedwater There have been no changes in the status of implementation of the third train of auxiliary feedwater. Plans for the addition of a third auxiliary feedwater pump to be installed during the current outage are progressing.
The components to be installed during the outage will be considered non-safety related and are being installed primarily as part of the dedicated shutdown system for fire protection. The third pump will be upgraded and integrated as a third train of the auxiliary feedwater system during the refueling/backfit outage for Cycle 10 operation.
TDI Diesel Generators Inspection of the TDI Diesel Generators continues.
Diesel generator number 1 has been returned to service after inspections and intercooler repair (to stop tube leaks).
Diesel generator number 2 has been taken out of service for the owners group/NRC recommended inspections.
Control Room Habitability Our last update on this subject indicated that prior to submitting a modification proposal, associated proposed technical specifications should be developed. It was anticipated that these would be submitted by February 7, 1986. It is now anticipated that the necessary approvals can be obtained in time for a March 17, 1986 submittal.
Supplement 1 to NUREG-0737 The schedule for completion of the Control Room Design Review (CRDR),
Regulatory Guide 1.97 and Safety Parameter Display System (SPDS) Evaluation remains as delineated in the August 29, 1985 revision of the ILS. The next scheduled NUREG-0737, Supplement 1 submittal will be the SPOS criteria on January 9, 1987.
GEH:5077F