ML20079M617
| ML20079M617 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/25/1984 |
| From: | Medford M SOUTHERN CALIFORNIA EDISON CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20079M621 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.1.1, TASK-TM NUDOCS 8401270376 | |
| Download: ML20079M617 (2) | |
Text
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1 Southern California Edison Company WE P, O. BOX 800 i
2244 WALNUT GROVE AVENUE ROSEM E AD, CAllFORNI A 91770 i
M.O. M E D FO R D T c L a pe.o ~ s January 25, 1984 in i n ">-"a
..~.. z.. ~uc a.. uc r~.,~a Director, Office of Nuclear Reactor Regulation Attention: Mr. George W. Knighton, Branch Chief Licensing Branch No. 3 U. S. Nuclear Regulatory Conmiission -
Washington, D.C.
20555 Gentlemen:
~
Subject:
Docket No. 50-362 San Onofre Nuclear Generating Station l
Unit 3 The purpose of this letter is to provide a summary of the initial test results of the leak reduction program. NUREG 0737, Item III.D.1.1, i
established requirements for developing a program to reduce leakage from piping systems outside containment that could contain highly radioactive fluid following an accident or transient. The program has two phases.
Phase I, the immediate leak reduction program, was conducted on a system-by-system basis by operating each system and leak testing individual components. On those components where significant leakage occurred, all necessary measures were taken to minimize or eliminate that leakage. The component leakage measured for the LSF systems tested was obtained by summing the minimum post-maintenance leakage achieved on each component. A final
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total leakage of 25 cc/ hour for all tested systems was ultimately calculated following completion of component maintenance.
Further discussion of leakage measurements obtained is included in the enclosure. This is well within the FSAR Chapter 15 (Table 15.6-19) assumption of 2486 cc/ hour used for offsite dose calculations.
Phase II involves a continuing leak reduction program of periodic visual inspections and integrated leak tests to reduce and maintain leakage to as-low-as practical levels. As leaks are detected, maintenance orders will be j
prepared and entered into the San Onofre Maintenance Management System.
Maintenance will be scheduled and performed depending on the seriousness of the leak, the Technical Specification operability requirements of the system, the availability of spare parts and the projected station outage schedule.
The immediate and proposed continuing leak reduction prt. grams were reported and discussed in SCE's Response to NRC Action Plan, NUREG 0660, San Onofre Nuclear Generating Station, Units 2 and 3; Item III.D.1.1:
" Primary Coolant Sources Outside the Containment Structure".
In Supplement 1 to the Safety Evaluation Report the staff concluded that the leak reduction and leak test programs meet the requirements of NUREG 0737, Item III.0.1.1, and are acceptable.
8401270376 840125 O
l PDR ADOCK 05000362 p
PDR Ill
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Mr. G.*W. Knight:n January 25, 1984 o
To implement the continuing leak reduction program, a station procedure has been written which requires system walkdowns. The program will attempt to coordinate system walkdowns with in-service inspection on a schedule based on the integrated refueling outage leak test in order to detect leaks that may otherwise not be evident.
The refueling interval leak test requirements of Technical Specification 6.8.4.a.11 are satisfied by four procedures which individually cover the HPSI, LPSI, CS, and PASS Systems.
These tests will be performed at the next refueling outage.
While the continuing leak reduction program will effectively reduce leakage, SCE expects the program to evolve through some significant changes during the first refueling cycle as experience gained is incorporated into program improvements. SCE has hired a consultant to review the program and the results obtained to determine what changes, if any, (i.e., frequency of walkdown inspections and integration into other ongoing programs) are necessary to improve the effectiveness of the program.
If you have any questions or comments, please contact me.
Very truly yours, h.h.k 4
1 Enclosure cc: Mr. H. Rood, Project Manager Licensing Branch No. 3 Mr. A. E. Chaffee NRC Site Inspector l
l 1