ML20133N214
| ML20133N214 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 01/10/1997 |
| From: | Gambhur S OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-97-001, LIC-97-1, NUDOCS 9701230202 | |
| Download: ML20133N214 (2) | |
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Omaha PublicPowerDistrict 444 South 16th Street Mall j
Omaha NE 68102-2247 l
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January 10, 1997 LIC-97-001 U. S. Nuclear Regulatory Commission l
Attn: Document Control Desk l
Mail Station P1-137 Washington, DC 20555
References:
1.
Docket No. 50-285 l
2.
Letter from OPPD (W. G. Gates) to NRC (Document Control Desk) dated June 23, 1993 (LIC-93-0119) 3.
Letter from 0 PPD (W. G. Gates) to NRC (Document Control Desk) dated January 13, 1994 (LIC-93-0304) 4.
Letter from OPPD (T. L. Patterson) to NRC (Document Control Desk) dated June 12, 1995 (LIC-95-0123)
SUBJECT:
Average Load Capacity Factor for Fort Calhoun Station (FCS) Cycle 16 The Omaha Public Power District (OPPD) monitors the long term load capacity f actor for FCS on a cycle-by-cycle basis to ensure that the current fluence / pressurized thermal shock (PTS) and other fluence dependent analyses remain valid.
In Reference 3, OPPD l
corm 11tted to notify the NRC of the average load capacity factor achieved since the start i
of Cycle 15.
Reference 4 provided data for Cycle 15.
The load capacity factor for Cycle 16 operation (including the refueling outage) was 0.82.
A revised fluence evaluation utilizing the ENDF-B/VI cross sections (per Reference 2) was completed in 1995. This evaluation, in conjunction with the load capacity factors of completed fuel cycles and projected capacity factors of future cycles, continues to be utilized to assess the projected end of life 10 CFR 50.61 RT,, value.
These projections assume future fuel cycle load capacity factors of 0.85.
The pressure-temperature (P-T) limit curves and the reactor vessel beltline materials l
have been reviewed based on the revised fluence evaluation and actual operation through I
the end of Cycle 17. The current Technical Specification P-T limits are still valid for Cycle 17 operation based on the fluence values used in the analysis for the 20 Effective Full Power Years (EFPY), as approved in Amendment 114 to Facility License No.
The welds and plate material in the reactor vessel beltline region are projected to remain below the 10 CFR 50.61 PTS screening criteria through the end of licensed operation.
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9701230202 970110 PDR ADOCK 05000205 P
PDR c5 5120 Employment with Equal Opportunity
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U. S. Nuclear Regulatory Commission LIC-97-001 l
Page 2 Please contact me if you have any questions.
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Sincerely, f
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S. K. Gambhir Division Manager Production Engineering TCM/tcm c:
Winston & Strawn L. J. Callan, NRC Regional Administrator, Region IV L. R. Wharton, NRC Project Manager W. C. Walker, NRC Senior Resident Inspector l
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