ML023230348

Site Core Operating Limits Report

ML023230348
Person / Time
Site:	Oconee
Issue date:	11/12/2002
From:	Rosalyn Jones Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML023230348 (7)

Text

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Duke Power 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 November 12, 2002 U.

S. Nuclear Regulatory Commission Document Control Desk Washington, D.

C.

20555 Subj ect:

Oconee Nuclear Site Docket No.

50-287 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 3, Cycle 20, Rev. 16.

Very uly yours, R

Jones Site, Vice President Oconee Nuclear Site Attachment www.duke-energy corn ADOI

NRC Document Control Desk November 12, 2002 Page 2 xc w/att:

Mr. L.

A. Reyes, Regional Administrator U.

S. Nuclear Regulatory Commission, Region II Mr.

L.

N. Q1shan, Project Manager Office of Nuclear Reactor Regulation Mr. Mel Shannon Senior Resident Inspector Oconee Nuclear Site

DISPOSION OF THE ORIGINAL DOCUMENT WILL BE TO

PRIORITY,

_THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS OTHERWISE IDENTIFIED BELOW

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____________ j __________________ I Duke Power Company DOCUMENT TRANSMITTAL FORM REFERENCE NUCLEAR GENERAL OFFICE OCONEE NUCLEAR STATION EXEMPTION CODE: M-5 RESP GROUP: N/E O3C20 COLR Page 1 of 1 DOCUMENT NO REMARKS:

DUKE DOCUMENT RELEASE EXEMPT FROM NUCLEAR MODIFICATION PROGRAM.

TOTAL PAGES: 4 Date:

10125102 Document Transmittal #:

DUK022980005 QA CONDITION 0

Yes [: No OTHER ACKNOWLEDGEMENT REQUIRED [] Yes IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO.

Duke Power Company 7800 Rochester Highway Document Management ON02DM Seneca, South Carolina 29672 Rec'd Ely Date 113 11-#

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ONEI-0400-70 Rev 16 Page 1 of 31 Duke Power Company Oconee 3 Cycle 20 Core Operating Limits Reporl QA Condition I hint~~_

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ONEI-0400-70 Rev 16 Page 2 of 31 Oconee 3 Cycle 20 Core Operating Limits Report Insertion Sheet for Revision 16 I

This revision is not valid until the end of operation for Oconee 3 Cycle 19.

1 Remove these Revision 15 pages 1 - 3, and 5 Effective Date Revision Log Pages Pages Revised Added Insert these Revision 16 pages 1 - 3, and 5 Pages Total Effective Deleted Pages Oconee 3 Cycle 20 revisions below 16 Oct-02 1-3,5 31 15 Nov-01 1-3 31 14 Nov-01 1-31 31 lOconee 3 Cycle 19 revisions below 13 Apr-O0 1-31 31 Oconee 3 Cycle 18 revisions below 12 Feb-00 1-4 31 11 Jun-99 1-3,31 31 10 Mar-99 1-31 32-38 31 9

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ONEI-0400-70 Rev 16 Page 3 of 31 Oconee 3 Cycle 20 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Repor for 03C20 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 allowable setpoints are documented in references 11 through 13. These limits are validated for use in 03C20 by references 14 through 16. The 03C20 analyses assume a design flow of 107.5% of 88,000 gpm per RCS pump, radial local peaking (FAh) of 1.714, an axial peaking factor (Fz) of 1.5, and an EOC L< 100 ppmB) Tavg reduction of up to 10 °F provided 4 RCPs are in operation and Tavg does not decrease below 569 OF.

The error adjusted core operating limits included in section I of the report incorporate all necessary uncertainties and margins required for operation of the 03C20 reload core.

1.1 References

1. Nuclear Design Methodology Using CASMO-3 / SIMULATE-3P, DPC-NE-1004P-A, 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-1001A, Revision 5, SER dated December 8, 2000.

4. Oconee Nuclear Station Core Thermal Hydraulic Methodology Using VIPRE-01, DPC-NE-2003P-A, SER dated July 19, 1989.

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, SER dated April 3, 1995.

7. UFSAR 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 Limit, OSC-4048, Revision 3, July 1998.

12. Power Imbalance Safety Limits 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. 03C20 Maneuvering Analysis, OSC-7727, Revision 4, October 2002.

15. 03C20 Specific DNB Analysis, OSC-7845, Revision 0, June 2001.

16. 03C20 Reload Safety Evaluation & IOCFR50.59, OSC-7959, Revision 1, November 2001.

ONEI-0400-70 Rev 16 Page 5 of 31 Oconee 3 Cycle 20 EFPD 0 to 426 426 to EOC Core Power Level, %FP Full Incore Out of Core Backup Incore

)

Steady State Operating Band Rod Index APSR Min Max Min 292+/- 5 300 30 292+/- 5 300 100

%WD Max 40 100 Quandrant Power Tilt Setpoints Steady State Transient 30-100 0-30 30-100 0-30 3.50 7.73 7.23 9.51 2.24 6.09 5.63 7.72 2.22 3.87 3.63 4.81 Referred to by TS 3.2.3.

Maximum 0- 100 16.67 14.22 10.07