ML20059F303
| ML20059F303 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 11/03/1993 |
| From: | Rosenblum R SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20059F306 | List: |
| References | |
| NUDOCS 9311040232 | |
| Download: ML20059F303 (2) | |
Text
. _..
1 fGF i
Southem Calihmia Edison Company 23 PARKER STREET
" " ' ' ^ " " " ' ' ' ' " *
.co..o osE~.w-m.~o-j November 3, 1993
~~.~.o ma -..m, I
I U. S. Nuclear Regulatory Commission Attention: Document Control Desk i
Washington, D.C.
20555 Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362 Amendment Application Nos. 135 and 119 Changes tn Technical Specification 3/4.6.3 Containment Isolation Valves San Onofre Nuclear Generating Station Units 2 and 3 Enclosed are Amendment Application Nos.135 and 119 to Facility Operating j
Licenses NPF-10 and NPF-15 for the San Onofre Nuclear Generating Station (SONGS) Units 2 and 3, respectively. These amendment applications consist of l
Proposed Change Number (PCN)-430. PCN-430 is being processed to revise the t
l operability requirements of containment isolation valves listed in. Technical Specification (TS) Table 3.6-1, Section D.
The associated Bases 3/4.6.3, i
j
" Containment Isolation Valves," are also revised.
The existing TS 3/4.6.3 " Containment Isolation Valves," considers all valves listed in Table 3.6-1, Section D operable when secured in their Engineered j
Safety Feature Actuation System (ESFAS) actuated position. For some m ives, such as check valves, valves with dual ESFAS functions (closed and open), and valves whose ESFAS position is closed, the requirements of the existing-TS are not appropriate.
I TS 3/4.6.3 is revised to require valves listed in Section D of Table 3.6-1 to be in an Action statement when secured in their ESFAS actuated position. The Action and Allowable Outage Time (A0T) for these valves are based on the l
conclusions of specific risk evaluations which assessed the contribution to the risks of core damage frequency and significant offsite release frequency when the valves are secured in their ESFAS actuated position. Administrative controls based on conclusions of the specific risk evaluations for the valves
~
j currently listed in TS Table 3.6-1, Section D have been implemented since l
April 1993 and will continue to be in effect until the NRC approves PCN-430.
040017 l
9311040232 931103 E
PDR ADOCK 05000361 Q 4W L
P PDR g
/.
Document Control Desk If you would like additional information on this Technical Specification change request, please let me know.
/
Sincerely, 7
} lH sn I
Enclosures cc:
B. H. Faulkenberry, Regional Administrator, NRC Region V NRC Senior Resident Inspector's Office, San Onofre Units 1, 2, and 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3 H. Kocol, California Department of Health Services l