ML20078F387

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Forwards Suppl 1 to Amend Applications 141 & 125 to Licenses NPF-10 & NPF-15,respectively,consisting of Proposed Change 402,changing TS 3.9.8.1, SDC & Coolant Circulation -- High Water Level & TS 3.9.8.2, Sdc...Low Water Level
ML20078F387
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 01/30/1995
From: Rosenblum R
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20078F389 List:
References
NUDOCS 9502020089
Download: ML20078F387 (2)


Text

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., m fDY Southem Calibmla Edison Company 23 PARKER STREET 1RVINE, CALIFORNIA 92718

, January 30, 1995 [fl.'.1.~.'o U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Docket Nos. 50-361 and 50-362 Supplement 1 to Amendment Application Nos. 141 and 125 Change to Technical Specification 3.9.8.1 " Shutdown Cooling and l Coolant Circulation -- High Water Level," Technical Specification  ;

3.9.8.2, " Shutdown Cooling and Coolant Circulation -- Low Water l Level," and the Refueling Operations, Bases: 3/4.9.8, " Shutdown i Cooling and Coolant Circulation" '

San Onofre Nuclear Generating Station Units 2 and 3 Enclosed are Supplement 1 to Amendment Application Numbers 141 and 125 to Facility Operating Licenses NPF-10 and NPF-15, respectively, for the San Onofre Nuclear Generating Station Units 2 and 3. These supplements to the amendment applications consist of Enclosure 1, Proposed Change Number 402, Supplement 1 (PCN-402, Supplement 1), and are requests to revise Technical Specification (TS) 3.9.8.1, TS 3.9.8.2, and their Bases. Also provided are 1 Enclosure 2, the proposed changes for the Technical Specification Improvement  !

Program (PCN-299) Technical Specifications, and Enclosure 3, RCS Heatup Rate i as a Function of Time After Shutdown and Cavity Level.

l PCN-402, Supplement 1, adds a phrase to require that the upper guide structure l be removed if both trains of the shutdown cooling system are to be removed '

from operation. The addition of this phrase ensures that the upper guide structure is not in place during testing of LPSI system components. Also, this phrase ensures that the condition currently requirea by the existing note is maintained. (i.e., T.S. 3.9.8.1 currently allows both trains of the shutdown cooling system to be removed from operation to support core alterations in the vicinity of the reactor pressure vessel hot leg. These core alterations can only be performed with the upper guide structure removed.)

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00 I 9502020089 950130 PDR ADOCK 05000361 P PDR i

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.a - . , 1 Document Control Desk fiV5 If you need additional infonnation on this Technical Specification change request, please let me know.

Sincerely, l' ,

I J ) M / W)

Enclosure t.! -

cc: L. J. Callan, Regional Administrator, NRC Region IV A. B. Beach, 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 1, 2 tad 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3 H. Kocol, California Department of Health Services

__________u._.