ML20135A271
| 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: |
| References | |
| NUDOCS 9612030143 | |
| Download: ML20135A271 (3) | |
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fM 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. is the 1995 Loss of Coolant Accident Margin Summary for San Onofre Nuclear Generating Station Units 2 and 3. (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 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.
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 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 for the-limiting large break LOCA evaluated under 10 CFR 50.59 for the 1995
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calendar year. Therefore, the limiting large break LOCA PCT as of the end of
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1995 is 2160*F, which is below the 10 CFR 50.46 acceptance criterion of 200* F..
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, provides a summary of the effect on PCT of the errors or changes 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
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
& J L Eak-Enclosures 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 J
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l Annual Report on ABB CE ECCS Performance Evaluation Models CENPD-279 Supplement 7 l
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