ML040550409

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Core Operating Limits Report for Oconee, Unit 1, Cycle 22, Rev. 21; Unit 2, Cycle 20, Rev. 20; and Unit 3, Cycle 21, Rev. 19
ML040550409
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 02/16/2004
From: Rosalyn Jones
Duke Energy Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ONEI-0400-50, Rev 21
Download: ML040550409 (18)
v • d • e


Text

-of Duke R. A. JONES

  • OPower. Vice President A Duke Energy Company Duke Power 29672 / Oconee Nuclear Site 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax February 16, 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 1, Cycle 22, Rev. 21, Unit 2, Cycle 20, Rev. 20, Unit 3, Cycle 21, Rev.19.

Very truly yours, R. A. Jones Site, Vice President Oconee Nuclear Site Attachment peso (

www. duke-energy. corn

NRC Document Control Desk February 16, 2004 Page 2 xc w/att: Mr. L. A. Reyes, 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

ots~rosmc)WOF THE ORIGINAL DOCUMENT WILL BE TO RTRYSuperRush THE TRANSWITTAL SIGNATURE UNLESS RECIPIENT IS Date: 02106104 PRIOROTHERWIS E IDENTIFIED BELOW Document Transmittal #: DUK040370006

$ 00620 DOC MGMT MICROFILM EC03C QP00813 DOC MGMT EC03C ORIGINAL Duke Power Company QACONDITION

  • Yes [- No

&6358 ONS REGUL COMPLIANCE ON03RC OTHER ACKNOWLEDGEMENT REQUIRED n Yes 4~67o0ONS MANUAL MASTER FILE ON03DM DOCUMENT TRANSMITTAL FORM-IFQA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE O06937 RRST CLAIR EC08G ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

REFERENCE NUCLEAR GENERAL OFFICE Duke Power Company OCONEE NUCLEAR STATION P.O. Box 1006 EXEMPTION CODE: M-5 Energy Center EC03C OCONEE I CYCLE 22 Charlotte, N.C OCONEE 2 CYCLE 20 OCONEE 3 CYCLE 21 CORE OPERATING LIMITS REPORT (COLR) Recd By Page 1 of I Date I I I I DOCUMENT NO QACOND REV #1DATE I DISTR CODE I 2 3 4 5 6 17 8 9 10 I" 12 113 114 115 TOTAL I L l I ONEI-0400-050 1 024- 02106104 1'OMD-27 j1 VI VI 4 ONEI-0400-051 1 06L. 02106104 ONEI-0400-070 1 019,02106/04 II SEE REMARKS P11 "4 8/l 404/6

/

REMARKS: DUKE DOCUMENT RELEASE EXEMPT FROM (NUCLEAR) MODIFICATION PROGRAM K S CANADY

    • PLEASE UPDATE PER THE REVISION INSTRUCTIONS" MANAGER NUCLEAR ENGINEERING BY:

J W SIMMONS JWS/AYB ECO8H

ONEI-0400-50 Rev 21

  • Page 1 of 33 Duke Power Company Oconee I Cycle 22 Core Operating Limits Report QA Condition I FOR INFORMATION ONLY RnEDNDAPPROMUMN.US Prepared By: -J. M. Sanders P I -,,0X Date: 4 _

74&1b

..h Checked By: G. M. Presnell 64:4-P,, Date: 9,- qLA -

CDR By: J. L. Abbott

  • 7, Date: Vmr _

Approved By: R. R. St. Clair AkR.f .SA444tok Date: 4. FCC0_ o4

Document No./ Rev. ONEI-0400-50 Rev. 21 Date February 4. 2004 Page No. page 2 of 33 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: eC.

'(Sponsor) pi& no R.. ,S4 ctm.Xr Date: a4. FeRLa4 CATAWBA Inspection Waived MCE (Mechanical & Civil) [] Inspected BylDate:

RES (Electrical Only) [l Inspected By/Date:

RES (Reactor) [l Inspected By/Date:

MOD [ Inspected By/Date:

Other ( ) D Inspected By/Date:

OCONEE Inspection Waived MCE (Mechanical & Civil) [3 Inspected By/Date:

RES (Electrical Only) Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD Inspected By/Date:

Other (_ ) Inspected By/Date:

MCGUIRE Inspecti on Waived MCE (Mechanical & Civil) 0 Inspected By/Date:

RES (Electrical Only) ] Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD [l Inspected By/Date:

Other (E ) Inspected By/Date:

ONEI-0400-50 Rev 21 Page 3 of 33 Oconee I Cycle 22 Core Operating Limits Report Insertion Sheet for Revision 21 I This revision is not valid until the end of operation for Oconee 1 Cycle 21.

Remove these revision 20 pages Insert these revision 21 pages 1 -4, 6 1 -4,6 Revision Log Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages t Oconee I Cycle 22 revisions below 21 Feb 2004 1 - ;6 - - 33 3.

20 Nov 2003 1 -32 33 - 33 Oconee 1 Cycle 21 revisions below 19 .Aug2003. 1, 2,:3 la - 32 18: Apr2002 1,2,4 - - 32

'17 Maar2002 1-31 32 - 32 lOconee 1 Cycle 20 revisions below 16 May2001 1-4 - - 31 15 Nov 2000 1-31 -- 31

)

ONEI-0400-50 Rev 21 Page 4 of 33 Oconee 1 Cycle 22 1.0 Error Adjusted Core Operating Umits The Core Operating Limits Report for 01C22 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 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 OF provided 4 RCPs are in operation and Tavg does not decrease below 569 OF.

The error adjusted core operating limits Induded in section 1 of the report incorporate all-necessary uncertainties and margins required for operation of the 01 C22 reload core.

1.1 References

1. Nuclear Design Methodology Using CASMO-3 I SIMULATE-3P, DPC-NE-1004P-A. Revision 0, SER dated November 23, 1992.
2. Oconee Nudear Station Reload Design Methodology II, DPC-NE-1 002A, Revision 1.

SER dated October 1, 1985.

3. Oconee NudearStation 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 Coee 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-10192-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. RELAP51MOD2-B&W - An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis', SER dated April 9,2002.
11. BAW-10227-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, OSC4048, 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-413, Revision 3, Febnuary2004.
16. 01C22 Specific DNB Analysis, OSC-8460, Revision 1. September2003.
17. 01C22 Reload Safety Evaluation. OSC-8471, Revision 0 November2003.

ONEI-0400-50 Rev 21 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- 300 100 100 QWandrant 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 ITS 3.2.3.

Correlation Slope (CS) .

1.15 Referred to by ITS 3.3.1 (SR 3.3.1.3).

ONEI-0400-51 Rev 20 Page 1of 32 Duke Power Company Oconee 2 Cycle 20 Core Operating Limits Report FOR INFORMATION ONLY QA Condition I

)

Not Reviewed er-Approved by GFAM 3.13 Prepared By: J. M. Sanders -

Date: 63 fia ZOOS 11 '

Checked By: G. M.Presnell A' Date: 2_4-b _2VoL, CDR By: J. L. Abbott Vou I.

V AaV Date: #FP if Approved By: R. R. St. Clair wi" Pf piNAl Date: .4 Fi O4 (e a 1. 1e4.r

Document No] Rev. ONEI-0400-51 Rev. 20 Date *Feburary2004 Page No. page la of 32 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: P s Q Xcr  : Date:

(Spoliso I I 'O CATAWBA Inspection Waived MCE (Mechanical & Civil) D Inspected By/Date:.

RES (Electrical Only) a Inspected By/Date:

RES (Reactor) [ Inspected By/Date:

MOD [ Inspected By/Date:

Other ( ) ] Inspected By/Date:

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

RES (Electrical Only) Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD Inspected By/Date:

Other ( ) D Inspected By/Date:

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

.RES (Electrical Only) 5 Inspected By/Date:

RES (Reactor) 5 Inspected By/Date:

MOD E Inspected By/Date:

Other ( ) S Inspected By/Date:

I1

ONEI-0400-51 Rev 20 Page 2 of 32 Oconee 2 Cycle 20 Core Operating Limits Report Insertion Sheet for Revision 20 I - This revision is not valid until the end of operation for Oconee 2 Cycle 19.

Remove these revision 19 pages Insert these revision 20 pages I - 3, 5 1 - 3, 5 Revision Log Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages Oconee 2 Cycle 20 revisions below

. 20. Feb 2004 1 -3,5 - - 33 19 Nov 2003 1-4,8-10,12-13,29 - - 33 18 Oct2002 .1-3,14,16,24,30 - - 32 17 Oct 2002 .1-31 32 . - 32 IOconee 2 Cycle 19 revisions below.

16 . - May.2001..1 - 31 -- 31 3 l Oconee 2 Cycle 18 revisions below 15 Apr2001. 1-4 - - 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

ONEI-0400-51 Rev 20 Page 3 of 32 Oconee 2 Cycle 20 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for 02C20 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 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 02C20 by references 14 through 16. The 02C20 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 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 02C20 reload core.

1.1 References

1. Nuclear Design Methodology Using CASMO-3 /SIMULATE-3P, DPC-NE-1004P-A, Revision 0, SER dated November23, 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. ONS Core Thermial 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 Apnl 3,1995.

7. UFSAR Chapter 15 Transient Analysis Methodology; DPC-NE-3005-PA, Revision 1, SER dated May25,1999.
8. DPC-NE-300OP-A, Thermal Hydraulic Transient Analysis Methodology, Rev. 2, SER dated October 14. 1998.
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-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 LUmit, OSC-4048, Revision 4, January 2001.
12. Power Imbalance Safety Linits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094, OSC-5604, Revision 2, October2001.
13. ATc and EOC Reduced Tavg Operation, OSC-7265, Rev. 1 Duke Power Co., June 2002.
14. 02C20 Maneuvering Analysis, OSC-8082, Revision 5. February 2004.
15. 02C20 Specific DNB Analysis, OSC-8103, Revision 0, June 2002.
16. 02C20 Reload Safety Evaluation, OSC-8182, Revision 1, November 2002.

ONEI-0400-51 Rev 20 Page 5 of 32 II Oconee 2 Cycle 20 Steady State Operating Band Rod Index APSR %WD EFPD Min Max Min Max 0 to 430 292+/- 5 300 30 40 430 to EOC 292 +/- 5 300 100 100 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 7.66 7.16 9.45 16.60 Out of Core 2.31 6.09 5.63 7.72 14.22
  • Backup Incore 2.24 3.87 3.63 4.81 10.07 Referred to by ITS 3.2.3.

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

ONEI-0400-70 Rev 19 Page 1 of 33 Duke Power Company Oconee 3 Cycle 21 Core Operating Limits Report QA Condition I FOR INFORMATION ONLY REVIEWED AND APPROVED BY'Atl 3.13 Not Rvid'wad or Approoved by CFAM 3.13 Prepared By: J. M. Sanders Date: 63'A Z6a4-1/P-Checked By: G. M. Presnell Q14LQP Date:

Q64- Date: . Off He

. VV Approved By: R. R. St. Clair

)p

. M-*3 -., Date.: 4 FEt c4

! WV.. IS. cIAt: C_

Document No./ Rev. ONEI-0400-70 Rev. 19 Date February 4. 2004 Page No. page 2 of 33 J

INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By. e.PI Lj*k Vf fu , If, -A .C Date: 0Z2a4}Cu (Sponsor)

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

RES (Electrical Only) D] Inspected By/Date:

RES (Reactor) a Inspected By/Date:

MOD [l Inspected By/Date:

Other ( l) Inspected By/Date:

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

RES (Electrical Only) Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD Inspected By/Date:

Other ( ) S Insiected By/Date:

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

RES (Electrical Only) [l Inspected By/Date:

RES (Reactor) 5 Inspected By/Date:

MOD [ Inspected By/Date:

Other ( l) Inspected By/Date:

ONEI-0400-70 Rev 19 Page 3 of 33 Oconee 3 Cycle 21 Core Operating Limits Report Insertion Sheet for Revision 19 This revision is not valid until the end of operation for Oconee 3 Cycle 20.

Remove these revision 18 pages Insert these revision 19 pages 1 -4,6 1 - 4, 6 Revision Log

) Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages Oconee 3 Cycle 21 revisions below

.19 Feb2004 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 Oconee 3 Cycle 19 revisions below 13 Apr.2000 1-31 - - 31

)

ONEI-0400-70 Rev 19 Page 4 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 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 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 peaking factor (Fz) of 1.5, and an EOC

(! 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 November23, 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. ONS Core Thermal Hydraulic Methodology Using VIPRE-01, DPC-NE-2003P-A, Revision 1, SER dated June 23,2000.
5. Thermnal 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-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-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, OS-8178, Revision 4, February 2004.
15. 03C21 Specific DNB Analysis, OSC-8220, Revision 0, October 2002.

I6. 03C21 Reload Safety Evaluation, OSC-8400, Revision 1, November2003.

ONEI-0400-70 Rev 19 Page 6 of 33 j

Oconee 3 Cycle 21 Steady State Operating Band Rod Index APSR %WD EFPD Min Max Min Max 0 to 445 292+/-5 300 30 40 445 to EOC 292 +/- 5 300 100 100 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 7.57 7.07 9.36 16.51 Out of Core 2.39 6.09 5.63 7.72 14.22

  • Backup Incore 2.26 3.87 3.63 4.81 10.07 Referred to by ITS 3.2.3.

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

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