ML032591072
| ML032591072 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/03/2003 |
| From: | Rosalyn Jones Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| DUK032400038, ONEI-0400-50, Revision 19 | |
| Download: ML032591072 (7) | |
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- *rPowere A Duke Energy Company R. A. JONES Vice President Duke Power 29672 / Oconee Nuclear Site 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax September 3, 2003 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555
Subject:
Oconee Nuclear Site Docket No. 50-269 Core Operating Limits Report (COLR)
Gentlemen:
Attached, pursuant to Oconee Technical Specifications 5.6.5, is an information copy of a revision to the Core Operating Limits Report for Oconee Unit 1, Cycle 21, Rev. 19.
Very t y yours, ones Site, Vice President Oconee Nuclear Site Attachment A,,C) D L www. duke-energy. corn
NRC Document Control Desk September 3, 2003 Page 2 xc w/att:
Mr. L. A. Reyes, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation Mr. Mel Shannon Senior Resident Inspector Oconee Nuclear Site X
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ONEI-0400-50 Rev 19 Page 1 of 32 Duke Power Company Oconee I Cycle 21 Core Operating UmIts Report FOR INFORMATION ONLY Q-A-Condition 1
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Doctmuent No. Rev. ONEI-0400-50 fRev, 19)
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ONEI-0400-50 Rev 19 Page 2 of 32 J
Oconee 1 Cycle 21 Core Operating Limits Report Insertion Sheet for Revision 19 lThis revision is not valid until the end of operation for Oconee 1 Cycle 20.
Remove these revision 18 pages 1,2 and 3 Insert these revision 19 pages 1,2 and 3 Q(o5 Effective Revision Date Revision Log Pages Added Pages Revised Pages Total Effective Deleted Pages
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Oconee I Cycle21 reaiisons7below_
19 Aug403 1,2, 3 la 32 18 Apr-02 1,2,4
.32 17 Mar-02 1-31 32 32 OconeeI. Cycle 20.revisions below 46 -
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Nov-00 131 31 Oconee 1 Cycle 19 revisions below 14 Oct00 1,2,3,5 31 13 Feb-00 1,2,3,4 31 12 Jul-99 1, 2, 3, 8, 31 10,13,31 11 May-99 1-31 31 Oconee 1 Cycle 18 revisions below 10 Mar-99 1 - 31 32-38 31 9
Feb-98 1,2,3,5,13, 38 16,17,32,36 8
Nov-97 1,2,3,5,10, 37 38 32 7
Aug-97 1 - 38
ONEI-0400-50 Rev 19 Page 3 of 32 Oconee I Cycle 21 1.0 Error Adjusted Core Operating Umrts The Core Operating Units Report for 01C21 has been prepared in accordance with the requirements of ITS 5.6.5. The core operating limits within this report have been developed using NRC approved methodology identified in references I through 10. The.RPS protective limits and maximum aflowable setpoints are documented In references 11 through 13. These limits are validated for use In 01C21 by references 14 through 16. The O1C21 analyses assume a design flow of 107.5% of 88,000 gpm per RCS pump, radial local peaking (FAh) of 1.714, and axial peaking factor (Fz) of 1.5, and an EOC (< 100 ppmB) Tavg reduction of up to 10 OF provided 4 RCPs are in operation and Tavg does not decrease below 569 'F.
The error adjusted core operating limits Included in section 1 of the report Incorporate all necessary uncertainties and margins required for operation of the 01C21 reload core.
1.1 References
- 1. Nuclear Design Methodology Using CASMO-3 SIMULATE-3P, DPC-NE-1004P-A, Revision 0.
SER dated November23,1992.
- 2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1002A, Revision 1,
$ER dated October 1,1985.
- 3. Oconee Nuclear Station Reload Design Methodology, NFS-1001A, Revision 4, SER dated July29, 1981.
- 6. Therrmal Hydrautic Statistical Core Design Metliodology, DPC-NE-2005P-A, Revision 2, SER dated June 8, 1999.
- 6. Fuel Mechanical Reload Analysis Methodology Using TACO3, DPC-NE-2008P-A, SER dated April 3,1995.
- 7..UFtAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-PA, RevisIon 1, SER dated May 25, 1999.
- 8. DPC-NE-3000P-A, Thermal Hydraulic Transient Analysis Methodology, Rev. 2, SER dated October 14,1998.
- 9. BAW-10192-PA, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, SER dated February 18,1997.
- 10. BAW-10227-PA, Evaluation of Advanced Cladding and Structural Material (M5) In PWR Reactor Fuel, SER dated February 4,2000.
- 11. Variable Low Pressure Safety Umit, OSC-4048, Revision 3, July 1998.
- 12. Power Imbalance Safety Umits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094, OSC-5604, Revision 1, November 1998.
- 13. ATc and EOC Reduced Tavg Operation, OSC-7265, Rev. 0, Duke Power Co., April 2001.
- 14. OIC21 Maneuvering Analysis, OSC-7940, Revision 4, August 2003.
- 15. 01C21 Specific DNB Analysis, OSC-7945, Revision 0, October2001.
- 16. 01C21 Reload Safety Evaluation, OSC-8046, Revision 1, August 2003.