ML13324A914

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Forwards Rev 9 to Description of Progress on Selected Ongoing Regulatory Projects at Facility,Including long-term Svc Seismic Upgrading,Fire Protection,Tdi Diesel Generators & Environ Qualification
ML13324A914
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 07/03/1986
From: Medford M
Southern California Edison Co
To: Lear G
Office of Nuclear Reactor Regulation
References
NUDOCS 8607090281
Download: ML13324A914 (3)


Text

Southern Callfornia Edison Company P. 0.

BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 M.O.MEDFORD TELEPHONE MANAGER, NUCLEAR LICENSING (818) 302-1749 July 3, 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 May 30, 1986 Enclosed with this letter is the ninth 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 8607090281 860703 PDR ADOCK 05000206 P

PDR

Enclosure PROGRESS ON SELECTED REGULATORY PROJECTS SAN ONOFRE UNIT 1 REVISION 9 Introduction The following is Revision 9 of the progress on selected regulatory projects at San Onofre Unit 1.

Long-Term Service Seismic Upgrading The final submittal regarding the Seismic Reevaluation of SONGS 1 was provided by letter dated June 19, 1986. Modifications required to upgrade systems and equipment were completed during the current outage.

Fire Protection The fire protection Appendix R modifications required for return to service have been or will be completed prior to entering Mode 2. These modifications assure compliance with Section III.G, III.J and III.0 of 10 CFR 50, Appendix R. Revised III.G Compliance Evaluations and new Requests for Exemptions were submitted to the NRC by letters dated June 6, 1986 and May 30, 1986, respectively. A follow-up Fire Protection Inspection Team was on site June 18 and 19, 1986 to resolve the open items from the Fire Protection Audit.

During this inspection, all return to service related open items from the audit were closed with the exception of the compliance evaluations which have been reviewed and approved by NRR. Additional concerns regarding housekeeping procedures have also been resolved and the revised procedures submitted to the NRC Region office for review.

Environmental Qualification During the current outage, SCE completed the replacement/upgrade of equipment for the Environmental Qualification Program.

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 has been installed during the current 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.

-2 TDI Diesel Generators The inspections of diesel generators (DG) No. 1 and No. 2 as originally planned have been completed. A report on the results of DG No. 2 inspections was submitted to the NRC on June 20, 1986. Based on inspection results for the No. 2 diesel generator turbochargers, supplemental inspections of two of the No. 1 diesel generator turbochargers were conducted. A supplement to our May 19, 1986 report on DG No. 1 inspection results will be provided later this month.

Control Room Habitability By letter dated March 28, 1986, Amendment Application No. 133 and descriptions of proposed modifications to the control room HVAC were submitted. The Amendment Application provides proposed technical specifications to be used in operating the modified HVAC.

As stated in recent meetings with the NRC staff, a revised proposal, with a final determination of the modified configuration, will be submitted by September 1, 1986.

From May 20-22, 1986, members of NRR and Region V staff performed inspections of the SONGS 1 control room HVAC system. This inspection resulted in an SCE commitment to provide a description of the current control room HVAC design basis.

The design basis submittal was provided on June 2, 1986.

As a result of subsequent meetings, additional information was required for the review of acceptability for return to service with the current control room HVAC.

This information was provided on June 26 and 29, 1986.

Supplement 1 to NUREG-0737 The schedule for completion of the Control Room Design Review (CROR),

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 SCE has submitted a response (dated June 20, 1986) to support deviation from guidance to install a reactor vessel level monitoring system.

GEH:5077F