ML050550307

Site, Core Operating Limits Report

ML050550307
Person / Time
Site:	Oconee
Issue date:	02/10/2005
From:	Rosalyn Jones Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ONEI-0400-50, Rev 23
Download: ML050550307 (7)

Text

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Duke (0Powero A Duke Energy Company RON A. JONES Vice President Oconee Nuclear Site Duke Power ONOI VP/ 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax February 10, 2005 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 or Oconee Unit 1, Cycle 22, Rev. 23.

Ver t uly yours, R..

o s Site, Vice President Ocone Nuclear Site Attachment www. dukepower.com 00

NRC Document Control Desk February 10, 2005 Page 2 xc w/att:

Mr. W. D. Travers, 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

ONEI-0400-50 Rev 23 Page 1 of 33 Duke Power Company Oconee 1 Cycle 22 Core Operating Limits Report QA Condition 1 c5t.

Prepared By:

Checked By:

G. M. Presnell 41. S1 y.,kL J. M. Sanders Date: l-3 ( - 2 CO5 Date:

/ ' 3 / - Z Date: )I In s Date: ;2II 4 CDR By: S. G. Siry 4 L I

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Approved By: R. R. St. Clair -Ig(,@$

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ONEI-0400-50 Rev 23 Page 3 of 33 Oconee 1 Cycle 22 Core Operating Limits Report Insertion Sheet for Revision 23 I

This revision is not valid until the end of operation for Oconee 1 Cycle 21.

l Remove these revision 22 pages Insert these revision 23 pages 1 -4, 6 1 - 4,6 Revision Log Effective Revision Date Pages Pages Pages Total Effective Revised Added Deleted Pages Oconee 1 Cycle.22 revisions below 23 Feb 2005 1 - 4 6-33 22 Dec 2004 1 - 3,30 33 21 Feb 2004 1 -4,6 33 20 Nov2003 1-32 33 33 Oconee 1 Cycle 21 revisIons below 19 Aug 2003 1,2, 3 la 32 18 Apr2002 1,2,4 32 17 Mar 2002 1-31 32 32 Oconee 1 Cycle 20 revisions below 16 May 2001 1-4 31 15 Nov 2000 1 -31 31

ONEI-040O-50 Rev 23 Page 4 of 33 Oconee 1 Cycle 22 1.0 Error Adjusted Core Operating Umits The Core Operating Umits Report for 01C22 has been prepared in accordance with the requirements of TS 5.6.5. The core operating limits within this report have been developed using NRC approved methodology identified In references 1 through 11. The RPS protective limits and maximum allowable setpoints are documented In references 12 through 14. These limits are validated for use in 01C22 by references 15 through 17. The 01C22 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 'F 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 01C22 reload core.

1.1 References

1. Nuclear Design Methodology Using CASMO-3 I SIMULATE-3P, DPC-NE-1004P-A, Revision 0, SER dated November23, 1992.

2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1 002A, Revision 1, SER dated October 1,1985.

3. Oconee Nuclear Station Reload Design Methodology, NFS-1001A, Revision 5, SER dated December 8, 2000.

4. ONS Core Thermal Hydraulic Methodology Using VIPRE-01, DPC-NE-2003P-A, Revision 1,

)

SER dated June 23,2000.

5. Thermal Hydraulic Statistical Core Design Methodology, DPC-NE-2005P-A, Revision 2, SER dated June 8,1999.

6. Fuel Mechanical Reload Analysis Methodology Using TACO3, DPC-NE-2008P-A, Revision 0, SER dated April 3, 1995.

7. UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-PA, Revision 2, SER dated September 24, 2003.

8. DPC-NE-3000P-A, Thermal Hydraulic Transient Analysis Methodology, Rev. 3, SER dated September 24, 2003.

9. BAW-1 01 92-PA, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, SER dated February 18, 1997.

10. BAW-1 01 64P-A, Rev. 4, RELAP5/MOD2-B&W - An Advanced Computer Program for Ught Water Reactor LOCA and Non-LOCA Transient Analysis, SER dated April 9,2002.

11. BAW-1 0227-PA, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel, SER dated February 4, 2000.

12. RPS RCS Pressure & Temperature Trip Function Uncertainty Analyses and Variable Low Pressure Safety Umit, OSC-4048, Revision 4, January 2001.

13. Power Imbalance Safety ULmits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094, OSC-5604, Revision 2, October 2001.

14. ATc and EOC Reduced Tavg Operation, OSC-7265, Rev. 1, Duke Power Co., June 2002.

15. 01C22 Maneuvering Analysis, OSC-8413, Revision 5, February 2005.

16. 01 C22 Specific DNB Analysis, OSC-8460, Revision 1, September 2003.

17. 01 C22 Reload Safety Evaluation, OSC-8471, Revision 3, February 2005.

ONEI-0400-50 Rev 23 Page 6 of 33 Oconee 1 Cycle 22 Steady State Operating Band Rod Index APSR %WD EFPD Min Max Min 0 to 433 292+/- 5 300 30 433 to EOC 292 +/-5 300 30 Quandrant Power Tilt Setpoints Steady State Transient Core Power Level, %FP 30 - 100 0 - 30 30 - 100 Full Incore 3.50 7.60 7.10 Out of Core 2.36 6.09 5.63 Backup Incore 2.26 3.87 3.63 Referred to byTS 3.2.3.

Max 40 40 0 - 30 9.39 7.72 4.81 Maximum 0 - 100 16.54 14.22 10.07 Correlation Slope (CS) 1'.15 Referred to by TS 3.3.1 (SR 3.3.1.3).