ML042660403

Site, Core Operating Limits Report (COLR)

ML042660403
Person / Time
Site:	Oconee
Issue date:	09/13/2004
From:	Rosalyn Jones Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML042660403 (8)

Text

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Duke rirPowere A Duke Energy Company RON A. JONES Vice President Oconee Nuclear Site Duke Power ON0I VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax September 13, 2004 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Subject:

Oconee Nuclear Site Docket No. 50-269, 50-270, 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 21, Rev. 20.

Ver t ly yours, R

Jones Site, Vice President O o e Nuclear Site Attachment www. dukepower. corn

-,5 I NRC Document Control Desk September 13, 2004 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

DISPOSITlON OF THE ORIGINAL DOCUMENT WILL BE TO PRIORITY SuperRush THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS OTHERWISE IDENTIFIED BELOW Date:

09102104 Document Transmittal #:

DUK042460008

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 Duke Power -;Company DOCUMENT TRANSMITTAL FORM REFERENCE, NUCLEAR GENERAL OFFICE OCONEE NUCLEAR STATION RESP GROUP: NE WORK ITEM: M-5 OCONEE 3 CYCLE 21 CORE OPERATING.LIMITS REPORT Page 1 of 1 QA CONDITION Yes E No OTHER ACKNOWLEDGEMENT REQUIRED a

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 By Date

.III DOCUMENT NO QACOND REV #1 DATE DISTR CODE 1 12 3

4 5

6 7

8 9

10 11 1 12 113 114 115 lTOTAL

.1.

1.

.. ONEI-0400-070 SEE REMARKS

'1 020 09/02/04 1I 11 11 NOMD-27 V1 VI VI 4

FOR INFOfOMATION dNLY REMARKS: DUKE DOCUMENT RELEASE EXEMPT FROM NUCLEAR MODIFICATION PROGRAM..

SEE PAGE 3 FOR FILING INSTRUCTIONS.

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

J W SIMMONS JWS/TER EC08H

ONEI-0400-70 Rev 20 Page 1 of 33 i

Duke Power Company Oconee 3 Cycle 21 Core Operating Limits Report QA Condition I I

Rev i =ewed orpp.roeby-FAM&.

Prepared By: J. M. Sanders V7.)

47411tgiParJ Date: O/ 42y L14-&

Checked By

,. G. M. Presnell it Date:

? - / - oV Date:

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CDR By: R. G. Chow l

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Approved By: R. R. St. Clair p

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4p Date :

Document No) Rev. ONEI-0400-70 Rev. 20 Date Septernber 3. 2004 Page No.

pate 2 of 33 INSPECTION OF ENGINEERING INSTRUCTIONS 4444-,-, C. - NLuz-Inspection Waived By:

Date:

(9ponsor)

)

CATAWBA Inspection Waived MCE (Mechanical & Civil)

D Inspected By/Date:

RES (Electrical Only) a]

Inspected By/Date:

RES (Reactor)

D Inspected By/Date:

MOD

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Inspected By/Date:

Other (

)

j Inspected By/Date:

OCONEE Inspection Waived MCE (Mechanical & Civil)

Inspected By/Date:

RES (Electrical Only) 2-Inspected By/Date:

RES (Reactor)

Inspected By/Date:

MOD Inspected By/Date:

Other (

)

S Inspected By/Date:

MCGUIRE Inspection Waived MCE (Mechanical & Civil)

El Inspected By/Date:

RES (Electrical Only)

[]

Inspected By/Date:

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D Inspected By/Date:

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FOR INFORMATION ONLY

ONEI-0400-70 Rev 20 Page 3 of.33 Oconee 3 Cycle 21 Core Operating Limits Report Insertion Sheet for Revision 20 Remove these revision 19 pages 1 - 4. 6 Insert these revision 20 pages 1 -4, 6 Revision Log Effective I

Revision Date Pages Revised Pages Pages Total Effective Added Deleted Pages EOconee 3 Cycle 21 revisions below 20 Sep2004*

1 -4.6 33 19 Feb 2004 1 -4, 6 33 18 Nov.2003 1-3,5 33 17 Apr. 2003 1 - 31 32 - 33 33.

Oconee 3:Cycle,20 revisions below.,:,

.16 Oct.2002 -

1-3.5 31 15' NoV."2001 1 - 3 31 14 Nov. 2001 1 -31 31 lOconee 3 Cycle 19 revisions below 13 Apr. 2000 1

31 FOR INFORMATION ONLY

ONEI-0400-70 Rev 20 Page4 of 33 Oconee 3 Cycle 21 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for 03C21 has been prepared in accordance with the requirements of ITS 5.6.5. The core operating limits within this report have been devbloped using NRC approved methodology identified In references 1 through 10. The RPS protective limits and maximum allowable setpoints are documented in references 11 through 13. These limits are validated for use in 03C21 by references 14 through 16. The 03C21 analyses assume a design flow of 107.5% of 88,000 gpm per RCS pump, radial local peaking (FAh) of 1.714. and axial pieaing factor (Fz) of 1.5, and an EQO (a 100 ppmB) Tavg reduction of up to 10 OF provided 4 RCPs are in operation and Tavg does not decrease below 569 OF.

The error adjusted core operating limits included in section 1 of the report incorporate all necessary uncertainties and margins required for operation of the 03C21 reload core.

1.1 References

1. Nuclear Design Methodology Using CASMO-3 / SIMULATE-3P, DPC-NE-1 004P-A, Revision 0.

SER dated November 23, 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, SER dated April 3,1995.

7. UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-PA. Revision 1, SER dated May25, 1999.

8. DPC-NE-3000P-A, Them-al Hydraulic Transient Analysis MethodologyFQoR2,I N FORMAT I0 N ON LY 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-1 0227-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 4, January 2001.

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

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

14. 03C21 Maneuvering Analysis, OSC-8178, Revision 6, September2004.

15. 03C21 Specific DNB Analysis, OSC-8220, Revision 0, October 2002.

16. 03C21 Reload Safety Evaluation, OSC-8400, Revision 1, November 2003.

I ONEI-0400-70 Rev 20 Page 6 of 33 Oconee 3 Cycle 21 EFPD 0 to 494 C.

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 Quandrant Power Tilt Setpoints Steady State Transient 30 - 100 0 - 30 30-100 3.50 7.57 7.07 2.39 6.09 t.63 2.26 3.87 3.63 Referred to by ITS 3.2.3.

Max 40 0-30 9.36 7.72 4.81 Maximum 0 - 100 16.51 14.22 10.07 Correlation Slope (CS) 1.15 Referred to by ITS 3.3.1 (SR 3.3.1.3).

FOR INFORMATION ONLY