ML20135A271

Transmits CENPD-279,Suppl 7, Annual Rept on Abb CE ECCS Performance Evaluation Models Final Rept

ML20135A271
Person / Time
Site:	San Onofre
Issue date:	11/26/1996
From:	Rainsberry J SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20135A274	List: ML20135A271 ML20135A296
References
NUDOCS 9612030143
Download: ML20135A271 (3)

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Southem Califomia Edison Company P. O. BOX 128 SAN CLEMENTE, CALIFORNIA 92674-0128 i g g ag aEna November 26, 1996- rey,e_

JCW ONOFRE NUCLEAR GENERATING ST ATION U. S. Nuclear Regulatory Commission i Attention: Document Control Desk ,

Washington, D.C. 20555  !

, Gentlemen:

Subject:

Docket Nos. 50-361 and 50-362 *

. Emergency Core Cooling System Annual 10 CFR 50.46 Report i San Onofre Nuclear Generating Station Units 2 and 3 j

This letter transmits the San Onofre Units 2 and 3 Annual Report for 1995 required by 10 CFR 50.46(a)(3)(ii). Provided as Enclosure 1 is the " Annual Report on ABB CE ECCS, Performance Evaluation Models, CENPD-279, Supplement 7" dated February 1996. Enclosure 2 is the 1995 Loss of Coolant Accident Margin Summary for San Onofre Nuclear Generating Station Units 2 and 3.

Enclosure 1 (CENPD-279, Supplement 7) describes the changes and errors in the Asea Brown Baveri/ Combustion Engineering (ABB/CE) codes and methodology for  !

Emergency Core Cooling System (ECCS) analysis in 1995. For the 1995 reporting l period, one error in the input processing for the COMPERC-II code for the I large break loss of coolant accident (LOCA) analysis was found and corrected.

There were no other changes made to the ABB/CE evaluation models for the large break, small break, or post-LOCA long term cooling calculations. l The correction of the error in COMPERC-II had no effect on the peak cladding temperature (PCT) for the large break.LOCA. The sum of the absolute .

magnitudes of the PCT changes for the large break LOCA from all reports to l date' continues to be less than l'F. No change occurred in the PCT for the '

small break LOCA or post-LOCA long term cooling.

There were no additional changes made to the plant specific input assumptions i for the-limiting large break LOCA evaluated under 10 CFR 50.59 for the 1995 /

calendar year. Therefore, the limiting large break LOCA PCT as of the end of 1995 is 2160*F, which is below the 10 CFR 50.46 acceptance criterion of /

200* F. .

Enclosure 2 provides a summary of the effect on PCT of the errors or changes [y)I ,

to the ECCS evaluation model reported under 10 CFR 50.46 for 1995 and the changes in 1995 to plant specific input assumptions for the limiting large ,

break LOCA evaluated under 10 CFR 50.59. 1he arithmetic sum of the PCT effects of both the 10 CFR 50.46 and 10 CFR 50.59 changes is a 0.0*F effect on the 2160*F large break LOCA analysis PCT.

9612030143 961126 PDR ADOCK 05000361 R PDR

', r Document Control Desk i If you have any questions or need additional information on this report, please let me know. f Sincerely,.

7~~D.Mhua-s Enclosures

& J L Eak-cc: L. J. Callan, Regional Administrator, NRC 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

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l Enclosure 1 Annual Report on ABB CE ECCS ,

Performance Evaluation Models CENPD-279 Supplement 7 l

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