ML052500406

Core Operating Limits Report, Cycle 21, Revision 24

ML052500406
Person / Time
Site:	Oconee
Issue date:	08/31/2005
From:	Rosalyn Jones Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ONEI-0400-051, Rev 24
Download: ML052500406 (8)

Text

RONALD A JONES Duke Vice President WIPowero Oconee Nuclear Site Duke Power ONOI VP / 7800 Rochester Hwy.

Seneca, SC 29672 864 885 3158 864 885 3564 fax August 31, 2005 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Subject:

Oconee Nuclear Site Docket No. 50-270 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 conee Unit 2, Cycle 21, Rev. 24.

Ve t y yours, R. A ones Site, Vice President Oconee Nuclear Site Attachment 4\:cl www. dukepower.com

NRC Document Control Desk August 31, 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. S.E. Peters Office of Nuclear Reactor Regulation Mr. Mel Shannon Senior Resident Inspector Oconee Nuclear Site

DISPOSION OF THE ORIGINAL DOCUMENT W.il BE TO PRIORITY SuperRush THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS Date: 08/25105 II OTHERWISE IDENTIFIED BELOW

1) 00620 DOC MGMT MICROFILM EC04T Document Transmittal #: DUK052370024

2) 00813 DOC MGMT EC04T ORIGINAL Duke Power Company QACONDITION

• Yes E No

3) 06358ONSREGULCOMPLIANCE ON03RC DO( OTHER ACKNOWLEDGEMENT REQUIRED n Yes

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

KtrCKMNUt NUCLEAR GENERAL OFFICE Duke Power Company OCONEE NUCLEAR STATION P.O. Box 1006 WORK ITEM: EXEMPTION M-5 Energy Center EC04T RESP GROUP: 7355 Charlotte, N.C RECORD RETENTION: 003587 OCONEE 2 CYCLE 21 CORE OPERATING LIMITS REPORT Rec'd By Page'i1 of I hef- Date l . . .

DOCUMENT NO QACOND REV #1DATE DISTR CODE 1 2 3 14 5 6 7 1 8 9 10 III 1 12 13 114 115 ITOTAL I I I I ONEI-0400-051 1 024 08125/05 NOMD-27 X V1 [VI VI 4 II 11 SEE REMARKS

,I:

OR INEC RMATION ONLY REMARKS: DUKE . . . . . . . . THOMAS .

DOCUMENT RELEASE EXEMPT FROM NUCLEAR MODIFICATION PROGRAM. C GEER SEE PAGE 3 FOR FILING INSTRUCTIONS. NUCLEAR STATION ENGR MANAGER GS-SVP NUCLEAR SUPPORT BY:

J W SIMMONS JWS/TER EC08H I

ONEI-0400-51 Rev 24 Page 1 of 33 FOR INFORMATION ONLY Duke Power Company Oconee 2 Cycle 21 Core Operating Limits Report QA Condition 1 Prepared By: J. D.Forster QNmr xID,, tzv Date: I(I ILe c;)T

_r Checked By: J. M. Sanders I - _

IN-- Date: l A V5 w

CDR By: M. E. Carroll '7/.a Date: 9//6/0 Approved By - Date : 6f -

Appr oed By4: Da e: o

Document No. / Rev. ONEI-0400-5 I Rev. 24 Date August 10. 2005 Page No. Page 2 of 33 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: Date: ___6/>

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I _ 1

ONEI-0400-51 Rev 24 Page 3 of 33 Oconee 2 Cycle 21 Core Operating Limits Report Insertion Sheet for Revision 24 This revision is not valid until the end of operation for Oconee 2 Cycle 20.

Remove these Revision 23 pages Insert these Revision 24 pages 1 - 4, 6 1 - 4, 6 Revision Log Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages Oconee 2 Cycle 21 revisions below l 24 Aug 2005 1 -4, 6 - 33

( 23 Mar2005 1-5 .-.-- 33 22 - Dec 2004 1 - 3,30 - 33 21 Apr2004 1 - 33 - 33 Oconee 2 Cycle 20 revisions below 20 Feb 2004 1 - 3,5 - - 33 19 Nov 2003 1-4,8-10,12-13,29 la - 33 18 Oct 2002 1-3,14,16,24,30 - - 32 17 Oct 2002 1 - 31 32 - 32 lOconee 2 Cycle 19 revisions below 16 May 2001 1 - 31 - - 31 Oconee 2 Cycle 18 revisions below 15 Apr2001 1-34 - - 31 14 Feb 2000 1 -4 -- 31 13 Nov 1999 1 - 31 -- 31 12 Sep 1999 1 - 31 -- 31 11 Apr 1999 1 - 4, 6 -- 31 10 Mar 1999 1 - 31 -- 31 j i ,

ONEI-0400-51 Rev 24 Page 4 of 33 Oconee 2 Cycle 21 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for 02C21 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 02C21 by references 15 through 17. The 02C21 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 5690F.

The error adjusted core operating limits included in section 1 of the report incorporate all necessary uncertainties and margins required for operation. of the 02C21 reload core.

1.1 References

1. Nuclear Design Methodology Using CASMO-3 / SIMULATE-3P, DPC-NE-1 004P-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-O1, DPC-NE-2003P-A, Revision 1, SER dated June 23,2000.

5. 7fliTiial Hidrauic Statistical Core Design Methodolod y iPC-NE-2005P-A, Revision 2, SER dated June 8,1999.7

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-10164P-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 Umits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094, OSC-5604, Revision 2, October2001.

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

15. 02C21 Maneuvering Analysis, OSC-8526, Revision 4, August 2005.

16. 02C21 Specific DNB Analysis, OSC-8561, Revision 0, November 2003.

17. 02C21 Reload Safety Evaluation, OSC-8609, Revision 1, August 2005.

ONEI-0400-51 Rev 24 Page 6 of 33 Oconee 2 Cycle 21 Steady State'Operating Band Rod Index APSR %WD EFPD Min Max Min Max 0 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

5~. . - . -OutC-6f.Cbre;.Z - . 2.36 6.09 .WE5.63 7

72 ... .-:.- 41220.0 Backup Incore 2.26 3.87 3.63 4.81 10.07 Referred to byTS 3.2.3 Correlation Slope (CS) 1.15 Referred to.by TS 3.3.1 (SR 3.3.1.3).