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

ADuke RON A. JONES

-r IorPowere Vice President Oconee Nuclear Site A Duke Energy Company 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

ONOF THE ORIGINAL DOCUMENT WILL BE TO PRIORITY SuperRush THE TRANSIMIrTAL SIGNATURE UNLESS RECIPIENT IS Date: 02/07/05 P_OTHERWIS E IDENTIFIED BELOW Document Transmittal # DUK050380053

1) 00620 DOC MGMT MICROFILM EC03C

2) 00813 DOC MGMT EC03C ORIGINAL Duke Power Company QACONDITION N Yes 2 No

3) 06358 ONS REGUL COMPLIANCE ON03RC

4) 06700 ONS MANUAL MASTER FILE ON03DM DOCUMENT TRANSMITTAL FORM OTHER ACKNOWLEDGEMENT REQUIRED D Yes IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE

5) 06937 RRST CLAIR EC08G ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

REFERENCE NUCLEAR GENERAL OFFICE Duke Power Company OCONEE NUCLEAR STATION P.O. Box 1006 WORK ITEM: EXEMPTION M-5 Energy Center EC04T RECORD RETENTION: 003587 Charlotte, N.C RESP GROUP: NE OCONEE 1 CYCLE 22 CORE OPERATING LIMITS REPORT Reced By Page 1 of I Date t .,

DOCUMENT NO QA COND l REV #1DATE l DISTR CODE 1 2 3 4 5 6 7 8 9 10 11 12 113 114 15 TOTAL t I ONEI-0400-050 I 023 02107105 NOMD-27 VI V1 VI VI 4 1I 11 SEE REMARKS 11 FOR !NFDRMATI10E X rorILY REMARKS: DUKE . . . . . . . THOMAS . . . . .

C GEER DOCUMENT RELEASE EXEMPT FROM NUCLEAR MODIFICATION PROGRAM.

SEE PAGE 3 FOR FILING INSTRUCTION FOR THIS DOCUMENT. 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

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VIR Oconee 1 Cycle 22 Core Operating Limits Report QA Condition 1 Prepared By: G. M. Presnell ml'77° Date: / - 3 1- 2c 5 I

Checked By: J. M. Sanders Date: / /

// / I CDR By: S.G.Siry )P. tviV I

Il hn5 Date: ,)

.I Approved By: R. R. St. Clair <7jel , _7 Date:

I . I 01/31/05 KON 15:35 FAX 864 885 3374 0NS TRAINING 10001 p.

Document No. I Rev. ONIET-0400-50 Rev. 23 Date January 31. 2005 Pa-e No. Page 2 of 33

)

INSPECTION OF ENGMNEERING INSTRUCTIONS Inspcetion Waived By: Date: 2A (Sponler)

CATAVBA Inspection Waived MCE (Mechanical & Civil) Inspected By/Date:

RES (Electrical Only) Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD Inspected By/Date:

Othcr ( ) E Inspccted By/Date:

OCONEE Inspection Waived MCE (Mechanical & Civil) Inspected By/Date:

RES (Electrical Only) 0 Inspected By/Date:

RES (Rcactor) El Inspectd By/Date: , (g,(o5 MOD cl Inspected By/Date:

Other (I__ ) E Tnspected By/Date:

MCGUIRE Inspection Waived MCE (Mechanical & Civil) El Inspected By/Date:.

RES (Electrical Only) E1 Inspected By/Date:

RES (Reactor) E Inspected By/Date:

MOD 0 Inspected By/Datc:

Other ( nspected In) By/D3te

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.

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

) Revision Date Revised Added 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 1a - 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 100 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 Steady State Operating Band Rod Index APSR %WD EFPD Min Max Min Max 0 to 433 292+/- 5 300 30 40 433 to EOC 292+/- 5 300 30 40 Quandrant Power Tilt Setpoints Steady State Transient Maximum Core Power Level, %FP 30 -100 0 - 30 30 -100 0 - 30 0 - 100 Full Incore 3.50 7.60 7.10 9.39 16.54 Out of Core 2.36 6.09 5.63 7.72 14.22 Backup Incore 2.26 3.87 3.63 4.81 10.07 Referred to by TS 3.2.3.

Correlation Slope (CS) 1.15 Referred to by TS 3.3.1 (SR 3.3.1.3).

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