ML050540573

Core Operating Limits Report

ML050540573
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
Download: ML050540573 (8)

Text

A Duke

-r IorPowere 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 Reportfor Oconee Unit 1, Cycle 22, Rev. 23.

yours, Fo'nbs Site, Vice President Nuclear Site Attachment www. dukepower. corn M

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

PRIORITY SuperRush THE TRANS P

_OTHERWIS

1) 00620 DOC MGMT MICROFILM EC03C

2) 00813 DOC MGMT EC03C ORIGINAL

3) 06358 ONS REGUL COMPLIANCE ON03RC

4) 06700 ONS MANUAL MASTER FILE ON03DM

5) 06937 R R ST CLAIR EC08G ON OF THE ORIGINAL DOCUMENT WILL BE TO IMIrTAL SIGNATURE UNLESS RECIPIENT IS E IDENTIFIED BELOW Duke Power Company DOCUMENT TRANSMITTAL FORM REFERENCE NUCLEAR GENERAL OFFICE OCONEE NUCLEAR STATION WORK ITEM: EXEMPTION M-5 RECORD RETENTION: 003587 RESP GROUP: NE OCONEE 1 CYCLE 22 CORE OPERATING LIMITS REPORT Page 1 of I Date:

02/07/05 Document Transmittal #

DUK050380053 QACONDITION N Yes 2 No OTHER ACKNOWLEDGEMENT REQUIRED D Yes IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

Duke Power Company P.O. Box 1006 Energy Center EC04T Charlotte, N.C Reced By Date t

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I ONEI-0400-050 I

SEE REMARKS 023 02107105 1I 11 11 FOR !NF NOMD-27 X

DRMATI10E VI r or V1 VI VI 4

ILY REMARKS: DUKE DOCUMENT RELEASE EXEMPT FROM NUCLEAR MODIFICATION PROGRAM.

SEE PAGE 3 FOR FILING INSTRUCTION FOR THIS DOCUMENT.

THOMAS C GEER NUCLEAR STATION ENGR MANAGER GS-SVP NUCLEAR SUPPORT BY:

J W SIMMONS JWSITER EC08H

-s ONEI-0400-50 Rev 23 Page 1 of 33 I

Duke Power Company Oconee 1 Cycle 22 Core Operating Limits Report QA Condition 1 VIR

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ONIET-0400-50 Rev. 23 Date January 31. 2005 Pa-e No.

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ONEI-0400-50 Rev 23 Page 3 of 33

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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.

Remove these revision 22 pages 1 - 4, 6 Insert these revision 23 pages 1 - 4, 6 Revision Log

)

Effective Pages Pages Revision Date Revised Added Pages Total Effective Deleted Pages Oconee 1 Cycle 22 revisions below 23 Feb 2005 1 - 4,6 33 22 Dec2004 1-3,30 33 21 Feb 2004 1 -4,6 33 20 Nov 2003 1 - 32 33 33 Oconee 1 Cycle 21 revisions below 19 Aug 2003 1,2, 3 1 a 32 18 Apr2002 1,2,4 32 17 Mar 2002 1-31 32 32 Oconee 1 Cycle 20 revisions below 16 May 2001 13-4 31 15 Nov 2000 1-31 31 I

ONEI-0400-50 Rev 23 Page 4 of 33 Oconee 1 Cycle 22 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for 01 C22 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 0 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/SIMULATE-3P, DPC-NE-1004P-A, Revision 0, SER dated November 23, 1992.

2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1002A, Revision 1, SER dated October 1, 1985.

3. Oconee Nuclear Station Reload Design Methodology, NFS-1 001 A, 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 0192-PA, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, SER dated February 18, 1997.

10. BAW-10164P-A, Rev. 4, RELAP5/MOD2-B&W - An Advanced Computer Program for Light 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 Limit, OSC-4048, Revision 4, January 2001.

13. Power Imbalance Safety Limits 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 EFPD 0 to 433 433 to EOC Core Power Level, %FP Full Incore Out of Core Backup Incore Steady State Operating Band Rod Index APSR %WD Min Max Min 292+/- 5 300 30 292+/- 5 300 30 Quandrant Power Tilt Setpoints Steady State Transient 30 -100 0 - 30 30 -100 3.50 7.60 7.10 2.36 6.09 5.63 2.26 3.87 3.63 Referred to by TS 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).

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