ML20112D436
| ML20112D436 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/03/1996 |
| From: | Nunn D SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20112D441 | List: |
| References | |
| NUDOCS 9606040322 | |
| Download: ML20112D436 (2) | |
Text
,
,g SOUTHf RN CALHORNIA EDISON 0 2 1"""
An LDISON IN7LRMHONAL Company June 3, 1996 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362 Proposed Technical Specification Change Number NPF-10/15-466 San Onofre Nuclear Generating Station Units 2 and 3
Reference:
Letter, Mel B. Fields (NRC) to Harold B. Ray (SCE), Subject,
" Issuance of Amendment for San Onofre Nuclear Generating Station, Unit No. 2 (TAC No. M86191) and Unit No. 3 (TAC No. M86192),"
dated, February 9,1996 Enclosed are Amendment Application Number 159 to Facility Operating License NPF-10, and Amendment Application Number 143 to Facility Operating License NPF-15, for the San Onofre Nuclear Generating Station (SONGS), Units 2 and 3.
The Amendment Applications consist of Proposed Technical Specification Change Number NPF-10/15-466 (PCN-466).
The proposed change is requested to reinstate provisions of the current SONGS Units 2 and 3 Technical Specifications revised as part of NRC Amendment Nos.
127 and 116, referenced above, for SONGS Units 2 and 3.
NRC Amendment Nos.
127 and 116 approved changes to'the SONGS Units 2 and 3 Technical Spccifications that adopted the recommendations of NUREG-1432, " Standard Technical Specifications Combustion Engineering Plants," submitted as part of Proposed Technical Specification Change Number NPF-10/15-299 (PCN-299). The l
proposed change would also revise requirements of the existing Technical Specifications for clarity. These changes were identified during preparation of the procedure changes necessary to implement NRC Amendment Nos. 127 and 116.
The proposed change would revise Technical Specification (TS) 3.3.1, " Reactor Protective Instrumentation--Operating," TS 3.3.8, " Containment Purge Isolation l
Signal (CPIS)," TS 3.3.10 " Fuel Handling Isolation Signal (FHIS)," TS 3.3.11,
" Post Accident Monitoring Instrumentation (PAMI)," TS 3.9.6, " Refueling Water l
Level," and TS 5.5.2.13, " Diesel Fuel Oil Testing Program." Specifically, the 1
l proposed change would remove exclusion of the power range source channel from l
the 92 day channel functional test of TS 3.3.1.
Setpoint allowable values l
specified in Surveillance Requirements (SRs) 3.3.8.2, and 3.3.8.3 for the Containment Gaseous Monitor, and specified in SR 3.3.10.2 for the required FHIS monitor, will be changed back to the limits currently specified.
9606040322 960603 PDR ADOCK 05000361 p
PDR P. O.11ox 128 San Clemente, CA 92672
,yg i
714 468-1480
/t I
Document Control Desk FHIS monitor, will be changed back to the limits currently specified. The number of instruments required to measure Reactor Coolant Inlet Temperature (Tc io) per loop, and Reactor Coolant Outlet Temperature (T,f1) per loop, will l
be revised from two per loop, to two.
The applicability o TS 3.9.6 would also be revised, and a note clarifying LC0 3.9.6 would be included.
I Additionally, SR 3.9.6.1 would be revised consistent with the changes to the i
LC0 and Applicability. The proposed change weuld also revise criteria for diesel fuel oil testing.
The changes described above, would reinstate provisions of the current SONGS Units 2 and 3 Technical Specifications.
l In addition, the proposed change would delete SONGS Unit 2 License Condition 2.C.(19)b, " Shift Manning," and revise TS 3.4.7, "RCS Loops--Mode 5, Loops Filled," for SONGS Units 2 and 3.
The SONGS Unit 2 license condition would be l
deleted as the shift manning requirements are addressed in the revised L
Administrative Controls section.
SR 3.4.7.2 of TS 3.4.7 will be revised te make the specified limit consistent with LC0 3.4.7, These changes revise requirements of the existing lechnical Specifications and are being made for clarity.
The Southern California Edison Company requests this amendment be issued by i
l July 15, 1996. This date-is consistent with our plans for implementation of NRC Amendment Nos. 127 and 116. This will provide adequate time for the l
necessary precedure changes and training on the new Technical Specifications.
If you would like additional information regarding this Amendment Application, please let me know.
Sincerely,
\\
~
1 Enclosure l
cc:
L. J.. Callan, Regional Administrator, NRC Region IV i
J. E. Dyer, Director, Division of Reactor Projects, Region IV K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units 2 & 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3 l
i i
.. -.