ML13324A932
| ML13324A932 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/01/1986 |
| From: | Medford M Southern California Edison Co |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TAC-60370 NUDOCS 8608050192 | |
| Download: ML13324A932 (3) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 M. 0. MEDFORD TELEPHONE MANAGER, NUCLEAR LICENSING August 1, 1986 (818) 302-1749 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 July 3, 1986 Enclosed with this letter is the tenth 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. It should be noted that this revision reflects the completion of the Long-Term Service Seismic Upgrade, Fire Protection and Environmental Qualification Projects. These projects will no longer have monthly reports.
We will continue to provide monthly updates of the remaining projects discussed in the enclosure for your information.
If there are any questions on these projects, please contact me.
Very truly yours, Enclosure 8608050192 860801 PDR ADOCK 05000206 F
Enclosure PROGRESS ON SELECTED REGULATORY PROJECTS SAN ONOFRE UNIT 1 REVISION 10 Introduction The following is Revision 10 of the progress on selected regulatory projects at San Onofre Unit 1.
Long-Term Service Seismic Upgrading The Seismic Reevaluation Program was completed during the refueling outage which began November 21, 1985. This item will no longer be reported in the monthly update.
Fire Protection Modifications and program changes associated with the applicable sections of 10 CFR 50 Appendix R were completed during the outage which began November 21, 1985. This item will also no longer be reported in the monthly update.
Environmental Qualification The Environmental Qualification Program was completed during the outage which began November 21, 1985. This item will also no longer be reported in the monthly update.
Third Train of Auxiliary Feedwater There have been no changes in the status of implementation of the third train of auxiliary feedwater. A third auxiliary feedwater pump was installed during the recent outage. The components installed during the outage are considered non-safety related and have been 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 A letter on the results of supplemental inspections of Diesel Generator No. 1 was submitted by letter dated July 21, 1986. SCE is continuing actions necessary to determine alternatives associated with reducing crankshaft transient torsional stresses. A revised Technical Specification on "slow" starts is currently being evaluated and is expected to be submitted in the fourth quarter.
-2 Control Room Habitability The short term NRC review of the Control Room HVAC design resulting from the inspections conducted during the week of May 20, 1986 has been completed. By letter dated July 8, 1986, a final information submittal was provided which summarized and updated the information previously provided during several telephone discussions. Agreement was reached regarding the dose assessment results and the HVAC surveillance program. It was also agreed that an additional short term modification would be made to provide air heaters for the system. The plans and schedules for resolving the long term issues related to Control Room HVAC design will be submitted by September 1, 1986.
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 Integrated Living Schedule. The next scheduled NUREG-0737, Supplement 1 submittal will be the SPDS criteria on January 9, 1987.
Inadequate Core Cooling There has been no change in this item since our last update. SCE previously submitted a response (dated June 20, 1986) to support deviation from guidance to install a reactor vessel level monitoring system.
GEH:5077F