ML20076E347
| ML20076E347 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/14/1991 |
| From: | Gates W OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-91-203R, NUDOCS 9108190271 | |
| Download: ML20076E347 (2) | |
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4 Ornaha Public Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 402/636-2000 August 14, 1991 LIC-91-203R U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-137 Washington, DC 20555
References:
1.
Docket No. 50-285 2.
Letter from 0 PPD (W. G. Gates) to NRC (Document Control Desk) dated April 1, 1991 (LIC-91-ll5R) 3.
Letter from 0 PPD (W. G. Gates) to NRC (Document Control Desk) dated March 30, 1990 (LIC-90-0265) 4.
Letter from OPPD (K. J. Morris) to NRC (Document Control Desk) dated October 16, 1909 (LIC-89-952)
Gentlemen:
SUBJECT:
Supplement to Annual Report on Loss of Coolant Accident (LOCA)
Emergency Core Cooling System (ECCS) Models Omaha Public Power District (0 PPD) committed in Reference 2 to provide supplemental information regarding errors or changes during 1990 associated with the Asea Brown Boveri-Combustion Engineering (ABB-CE) LOCA/ECCS models.
The commitment to supplement Reference 2 was necessary because at that time OPPD had not received ABB-CE's 1990 annual report on LOCA/ECCS models.
The ABB-CE 1990 annual report on LOCA/ECCS models was received by 0 PPD on August 7, 1991.
During 1990 ABB-CE discovered and corrected an error in the BORON code which is used to calculate boric acid in the reactor core after a LOCA.
This error was evaluated and the determination was made that no change in peak clad temperature (PCT) resulted.
The cumulative changes in PCT for large break LOCA, including the two previous annual notifications (References 3 and 4), is a reduction of less than l'F in the PCT.
There have been no changes in the small break LOCA results or model to date.
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U. S. Nuclear Regulatory Commission LIC-91-203R
- Page 2 No significant changes, as defined by 10 CFR 50.46, were implemented in 1990 for the fort Calhoun Station LOCA analyses.
Therefore, no additional actions beyond providing this supplemental information are required.
If you have any questions, please contact me.
Sincerely, 4&. ). Narbts W. G. Gates Division Manager Nuclear Operations WGG/sel c:
LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator, Region IV W. C. Walker, NRC Project Manager R. P. Mullikin, NRC Senior Resident Inspector d
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