ML032591072

Core Operating Limits Report, Cycle 21, Revision 19

ML032591072
Person / Time
Site:	Oconee
Issue date:	09/03/2003
From:	Rosalyn Jones Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
DUK032400038, ONEI-0400-50, Revision 19
Download: ML032591072 (7)

Text

- bDuke w- R. A. JONES

- *rPowere 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 September 3, 2003 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 Report for Oconee Unit 1, Cycle 21, Rev. 19.

Very t y yours, ones Site, Vice President Oconee Nuclear Site Attachment A,,C)DL-www. duke-energy. corn

NRC Document Control Desk September 3, 2003 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 X

PRIORrFY %pe" us OTh! ftiS1TLSO VN I Date: O8/08IU3 I 1)WS2M=CFMM:FDU~fILN EDIAREC03C, Documn~et Tranermittl M DUK032400038 2)C0Wt3 DOG tVWTEC3C CR1 QA CODtMMON OTHERt ACKNOWLEDOMMMT IREGUMO. rlYes

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CONE OPERATING luMIt RtPORT Reed By -

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...IAO F.I FOR INFCIRMATION ONLY REMARKS: DUKE DOCUMENT RELEASE EXEMPT FROM NUCLEAR 10ODIFICATlON PROGRAM. K S CANADY MANAGER NUCLEAR ENbINEERING BY:

J W. SIMMONS JWS/TER EC08H

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ONEI-0400-50 Rev 19 Page 1 of 32 Duke Power Company Oconee I Cycle 21 Core Operating UmIts Report FOR INFORMATION ONLY Q-A-Condition 1

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Not Reviewed or Approved by CFAM 3.13 Prepared By'. J. D.: F6rster n. 6N 4LO I -) Date: asplO(tX2&

Checked By: L. D. McClain L r"" - - Plql 06-16 OOL&OM Date: 26}A 9A'5 CDR By: R. Q. Huynh I, I'd,. __ &Aj_:no Date: £/Z7-3 !

r-r---v Approved By: R.R.St. Clair // Dat Date: 74f 76003

I - Doctmuent No. Rev. ONEI-0400-50 fRev, 19)

Date August 26.2003 Page No. la of 32 I. .INSPECTION OF ENGINEERING I$4STRUCTIONS Inspection Waived By (SponW  : *' -

Date: -f h CATAWBA Inspection Waived MCE (Mechanical & Civil) Q Inspected By/Date:

RES (Electrical Only) - Inspected By/Date:

RES (Reactor) Q Inspected By/Date:

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Other( Inspected ByDate:

OCONEE Inspection Waiv -

MCE (Mechanical & Civil) Inspected By/Date:

j RES (Electrical Only) 21 Inspected By/Date:

RES (Reactor) Inspected By/Date:

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Oer ( ) Inspected By/Date:

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

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.,- Ml t-ONEI-0400-50 Rev 19 Page 2 of 32 J

Oconee 1 Cycle 21 Core Operating Limits Report Insertion Sheet for Revision 19 lThis revision is not valid until the end of operation for Oconee 1 Cycle 20.

Remove these revision 18 pages Insert these revision 19 pages 1,2 and 3 1,2 and 3 Q(o5 Revision Log Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages

) Oconee I Cycle21 reaiisons7below_

19 Aug403 1,2, 3 la - 32 18 Apr-02 1,2,4 - - .32 17 Mar-02 1-31 32 - 32 OconeeI. Cycle 20.revisions below 46- M

.aybC 1 _

- 31 l

1: Nov-00 131 - - 31 Oconee 1 Cycle 19 revisions below 14 Oct00 1,2,3,5 - - 31 13 Feb-00 1,2,3,4 - - 31 12 Jul-99 1, 2, 3, 8, - - 31 10,13,31 11 May-99 1-31 - - 31 Oconee 1 Cycle 18 revisions below 10 Mar-99 1 - 31 - 32-38 31 9 Feb-98 1,2,3,5,13, - - 38 16,17,32,36 8 Nov-97 1,2,3,5,10, 37 - 38 32 7 Aug-97 1 - 38 -

ONEI-0400-50 Rev 19 Page 3 of 32 Oconee I Cycle 21 1.0 Error Adjusted Core Operating Umrts The Core Operating Units Report for 01C21 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 aflowable setpoints are documented In references 11 through 13. These limits are validated for use In 01C21 by references 14 through 16. The O1C21 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 10OF 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 01C21 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,

$ER dated October 1,1985.

3. Oconee Nuclear Station Reload Design Methodology, NFS-1001A, Revision 4, SER dated July29, 1981.

! 4. ONS Core Thermal Hydraulic Methodology Using ViPRE-01, DPC-NE-2003P-A, SER dated July 19,1989.

6. Therrmal Hydrautic Statistical Core Design Metliodology, 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. .UFtAR 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 Umit, OSC-4048, Revision 3, July 1998.

12. Power Imbalance Safety Umits 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. OIC21 Maneuvering Analysis, OSC-7940, Revision 4, August 2003.

15. 01C21 Specific DNB Analysis, OSC-7945, Revision 0, October2001.

16. 01C21 Reload Safety Evaluation, OSC-8046, Revision 1, August 2003.