ML022240123

Duke Energy Corp., Core Operating Report for Catawba Unit 2 Cycle 12, Revision 21

ML022240123
Person / Time
Site:	Catawba
Issue date:	07/31/2002
From:	Gordon Peterson Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML022240123 (9)

Text

Duke O Power A Duke Energy Company GARY R. PETERSON Vice President Catawba Nuclear Station Duke Power CN01 VP / 4800 Concord Rd.

York, SC 29745 803 831 4251 803 831 3221 fax grpeters@duke -energy. corn July 31, 2002 U.S. Nuclear Regulatory Commission ATTENTION:

Document Control Desk Washington, D.C.

20555-0001

Subject:

Duke Energy Corporation Catawba Nuclear Station Unit 2 Docket No.: 50-414 Core Operating Limits Report (COLR)

Catawba Unit 2 Cycle 12, Revision 21 Attached, pursuant to Catawba Technical Specification 5.6.5, is an information copy of the Core Operating Limits Report for Catawba Unit 2 Cycle 12, Revision 21.

This letter and attachment do not contain any commitments.

Please direct any questions or concerns to George Strickland at (803) 831-3585.

G.

R.

Peterson Attachment www. duke-energy. corn

U.

S. Nuclear Regulatory Commission July 31, 2002 Page 2 xc w/att:

L.

A.

Reyes U.

S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St.,

SW, Suite 23T85 Atlanta, GA 30303 C.

P.

Patel NRC Senior Project Manager (CNS)

U.

S. Nuclear Regulatory Commission Mail Stop 0-8H12 Washington, DC 20555-0001 D.

J.

Roberts Senior Resident Inspector (CNS)

U.

S. Nuclear Regulatory Commission Catawba Nuclear Site

CNEI-0400-25 Page 1 of 27 Revision 21 Catawba Unit 2 Cycle 12 Core Operating Limits Report Revision 21 July 2002 Duke Power Company Date Prepared By:

Checked By:

Checked By:

Approved By:

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7/:Z.V Y/o 7 AM 2-QA Condition 1 The information presented in this report has been prepared and issued in accordance with Catawba Technical Specification 5.6.5.

CNEI-0400-25 Page 2 of 27 Revision 21 Catawba 2 Cycle 12 Core Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 21 Revision 21 of the Catawba Unit 2 COLR must be implemented to meet the requirements of Technical Specification Amendment 192.

CNEI-0400-25 Page 3 of 27 Revision 21 Catawba 2 Cycle 12 Core Operating Limits Report REVISION LOG Revision Revisions 1-13 Revision 14 Revision 15 Revision 16 Revision 17 Revision 18 Revision 19 Revision 20 Revision 21 Effective Date N/A August 1998 October 1998 December 1998 February 2000 February 2001 September 2001 September 2001 July 2002 Pages Affected N/A N/A N/A N/A N/A N/A ALL 1,2,3,4,25,26,27 1-4, 5a, 5b, 5c COLR C2C06 - C2C09 C2C 10 COLR C2C 10 COLR rev 1 C2C10 COLR rev 2 C2CI1 COLR C2C 11 COLR rev 1 C2C12 COLR C2C12 COLR rev I C2C 12 COLR rev 2

CNEI-0400-25 Page 4 of 27 Revision 21 Catawba 2 Cycle 12 Core Operating Limits Report INSERTION SHEET FOR REVISION 21 Remove pages Insert Rev. 21 pages 1,2,3,4 1,2,3,4,5a,5b,5c

CNEI-0400-25 Page 5a of 27 Revision 21 Catawba 2 Cycle 12 Core Operating Limits Report 1.1 Analytical Methods The analytical methods used to determine core operating limits for parameters identified in Technical Specifications and previously reviewed and approved by the NRC are as follows.

1. WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," (W Proprietary).

Revision 0 Report Date: July 1985 Not Used for C2C12

2. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code, "(_W Proprietary).

Revision 0 Report Date: August 1985

3. WCAP-10266-P-A, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE", (W Proprietary).

Revision 2 Report Date: March 1987 Not Used for C2C12

4. WCAP-12945-P-A, Volume I and Volumes 2-5, "Code Qualification Document for Best Estimate Loss of Coolant Analysis," (W Proprietary).

Revision: Volume 1 (Revision 2) and Volumes 2-5 (Revision 1)

Report Date: March 1998

5.

BAW-10168P-A, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," (B&W Proprietary).

Revision 1 SER Date: January 22, 1991 Revision 2 SER Dates: August 22, 1996 and November 26, 1996.

Revision 3 SER Date: June 15, 1994.

Not Used for C2C12

CNEI-0400-25 Page 5b of 27 Revision 21 Catawba 2 Cycle 12 Core Operating Limits Report 1.1 Analytical Methods (continued)

6. DPC-NE-3000PA, "Thermal-Hydraulic Transient Analysis Methodology," (DPC Proprietary).

Revision 2 SER Date: October 14, 1998

7.

DPC-NE-3001PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).

Revision 0 Report Date: November 1991

8. DPC-NE-3002A, "FSAR Chapter 15 System Transient Analysis Methodology".

Revision 3 SER Date: February 5, 1999

9. DPC-NE-2004P-A, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," (DPC Proprietary).

Revision I SER Date: February 20, 1997

10. DPC-NE-2005P-A, "Thermal Hydraulic Statistical Core Design Methodology," (DPC Proprietary).

Revision I SER Date: November 7, 1996

11. DPC-NE-2008P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3," (DPC Proprietary).

Revision 0 SER Date: April 3, 1995

12. DPC-NE-2009-P-A, "Westinghouse Fuel Transition Report," (DPC Proprietary).

Revision 0 SER Date: September 22, 1999

13. DPC-NE-1004A, "Nuclear Design Methodology Using CASMO-3/SIMULATE-3P."

Revision I SER Date: April 26, 1996

CNEI-0400-25 Page 5c of 27 Revision 21 Catawba 2 Cycle 12 Core Operating Limits Report 1.1 Analytical Methods (continued)

14. DPC-NF-2010A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design."

Revision 0 Report Date: June 1985

15. DPC-NE-201 IPA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).

Revision 0 Report Date: March 1990