ML13324A901
| ML13324A901 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/25/1986 |
| From: | Medford M Southern California Edison Co |
| To: | Lear G Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13324A902 | List: |
| References | |
| NUDOCS 8606270112 | |
| Download: ML13324A901 (2) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 M. 0. MEDFORD June 25 1986 TELEPHONE MANAGER. NUCLEAR LICENSING June 25, (818) 302-1749 Director, Office of Nuclear Reactor Regulation Attention: G. E. Lear, Director PWR Project Directorate No. 1 U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-206 Additional Information Supporting Amendment Application No. 132 San Onofre Nuclear Generating Station Unit 1
Reference:
Letter, Robert Dietch, SCE, to H. R. Denton, NRC, dated November 20, 1985 Enclosed with the referenced letter was SCE's Amendment Application No. 132.
That amendment proposed changes to Technical Specifications (T.S.)
4.2.3, "Safety Injection Hydraulic Valve Testing," and 4.2.1, "Safety Injection and Containment Spray System Periodic Testing."
The changes would eliminate the interim T.S. 4.2.3 requiring plant shutdown every 92 days and replace it with a specification on the acceptable valve actuation times for the hydraulically actuated valves in T.S. 4.2.1.
As a result of discussions with members of the NRC staff, we have contracted an independent party to review the results of the interim testing and the proposed modifications to the T.S. In particular, it was requested that the differences between a full flow "hot" SIS test, and a no flow "cold" test be evaluated. Enclosure 1 provides this consultant's report for your review. The conclusions of the report are.that the root causes of the previous valve failures have been eliminated and that the proposed test is adequate for long term surveillance.
The report additionally recommends that particular attention be given to verification of successful operation of the HV-851 body relief solenoid valves, SV-2900 and SV-3900. Under the interim program, successful operation of these valves was verified. It will continue to be verified in future HV-851 testing. It should also be noted that these valves are being included in the Inservice Testing Program as requiring a quarterly full stroke test.
8606270112 860625 PDR ADOCK 05000206 P
Mr. G. E. Lear
-2 includes responses to several additional questions discussed with members of the NRC staff. These questions concern other aspects of system operation and testing not necessarily directly connected with the HV-851 valves.
If you have any questions, please let me know.
Very truly yours, Enclosures cc:
F. R. Huey, USNRC Resident Inspector, Units 1, 2 and 3
- 3. B. Martin, NRC Region V, Regional Administrator
- 3. 0. Ward, California Department of Health Services