ML20101L063
| ML20101L063 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/30/1992 |
| From: | Gates W OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-92-207R, NUDOCS 9207060237 | |
| Download: ML20101L063 (2) | |
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Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 402/636-2000 June 30, 1992 LIC-92-207R V. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station Pi-137 Washington, DC 20555
References:
1.
Docket No. 50-285 2.
Letter from NRC (D. L. Wigginton) to OPPD (W. G. Gates) dated March 2, 1992 3.
Letter frem OPPD (W. G. Gates) to NRC (Document Control Desk) dated January 9, 1992 (LIC-91-319R)
Gcntlemen:
SUBJECT:
Resolution of Follow-up Items for Elevated Ambient Air Tempersture Effects on the Fort Calhoun Station Emergency Diesel Generators (EDGs)
Omaha Public Power District (OPPD) committed in Reference 3 to complete two actions by June 30, 1992.
These items and the actions taken are noted below.
(1)
Determine the frequency of a preventive maintenance (PH) activity for EDG radiator inspection cnd cleaning to ensure optimum coeling system performance.
Based on equipment configuration and past experience, inspection and cleaning of the EDG radiators will be perfvrmed as a PM activity on a ref ueling outage frequency.
This PH frequency may be adjusted in the future based on operating and inspection results.
(2)
Generate a PH to ensure that the seasonal coolant changanut be maintained to assure hot weather capability of the ED'is.
Implementation of actions during the 1992 refueling outage to enhance EDS performar.ce may have obviated thc need for seasonal coolant changeout. As planned, OPPD replaced the existing 8-bladed radiator fans with 12-bladed assemblies.
This increased the air flow through the radiators, thereby reducing jacket water temperatures.
Also. a modification remcVed a non safety-related large load from EDG-2. This improved the upper ambient air temperature limits substantially for EDG-2.
9207060237 920530 PDR. ADOCK 05000285 p
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U. S. fiuclear Regulatory Commission LIC-92-207R Page 2 Based on the above noted enhancements, an engineering calculation and 10 CFR 50.59 safety evaluation have been completed.
They demonstrate acceptability of using ethylene glycol solution as coolant in all seasons, with resulting cmbient air upper temperature limits of 104'F for EDG-1 and 110 F for EDG-2.
This is a temporary change from the previous licensing basis limits of 110*F for both EDG-1 and EDG-2 noted in Reference 2.
OPPD plans to perform hot weather testing of EDG-1 and CDG-2 during the summer of 1992 to verify tha 2agineering evaluation results. The testing and subsequent evaluation ct the results will be used towards raising the EDG-1 limit to the OPPD goal of 110 F for both EbG-1 and EDG-2. OPPD will provide a summary of the hot weather testing results and any resultant actions to the NRC by October 31, 1992.
If you should have any questions, please contact me.
Sincerely, dv..N. [h W. G. Gates Division Mar,ager Nuclear Operations WGG/grc c:
LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, HRC Regional Administrator, Region IV R. P. Mullikin, NRC Senior Resident Inspecto-4 S. D. Bloom, NRC Acting Project Manager 4
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