W3F1-2006-0059, Core Operating Limits Report - Cycle 14 Revision 0 Change 1

Core Operating Limits Report - Cycle 14 Revision 0 Change 1

ML063130046
Person / Time
Site:	Waterford
Issue date:	11/07/2006
From:	Murillo R Entergy Nuclear South, Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2006-0059
Download: ML063130046 (8)

Text

Entergy Nuclear South Entergy Operations, Inc.

17265 River Road Killona, LA 70057-3093 Etergy Tel 504-739-6715 Fax 504-739-6698 rmuriil@entergy.com Robert J. Murillo Licensing Manager Waterford 3 W3F1-2006-0059 November 7, 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 SUBJEQTL,.,> ,Core Operating Limits Report- Cycle 14 Revision 0 Change 1 Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38 REFERENCE -S: 1. Entergy Letter to the NRC dated May 17, 2005, "Core Operating Limits Report - Cycle 14 Revision 0" (W3F1-2005-0033)

Dear Sir or Madam:

Waterford 3 Technical Specification 6.9.1.11.3 requires submittal of the Core Operating Limits Report (COLR) for each reload cycle, including any mid-cycle revisions or supplements. Revision 0 for Cycle 14 COLR was previously submitted per Reference 1 above.

Please find attached Change 1 to Revision 0 of the COLR for Waterford 3 Cycle 14. In Change 1, TS 6.9.1.11, "Core Operating Limits Reports COLR," was revised to add a methodology that will allow the use of zirconium diboride (ZrB2) absorber coating on fuel pellets planned for Waterford 3 Cycle 15. This change was authorized by NRC issuance of Amendment 210 on October 6, 2006.

If you have any questions concerning this submittal, please contact R.L. Williams at (504) 739-6255.

There are no commitments contained in this submittal.

Sincerely, 1R.J. Murillo RJM/RLW/cbh

Attachment:

1. COLR Cycle 14 Revision 0 Change 1

W3F17-2006-0059 Page 2 of 2 cc: (w/Attachment)

Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. Mel B. Fields MS O-7D1 Washington, DC 20555-0001 (w/o Attachment 1)

Wise, Carter, Child & Caraway ATTN: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn ATTN: N.S. Reynolds 1700 K Street, NW Washington, DC 20006-3817 Morgan, Lewis & Bockius LLP ATTN: T.C. Poindexter 1111 Pennsylvania Avenue, NW Washington, DC 20004 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. O. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers 95 Glastonbury Blvd - Suite 300 Glastonbury, CT 06033-4443

Attachment I to W3FI-2006-0059 COLR Cycle 14 Revision 0 Change 1

CORE OPERATING LIMITS REPORT CYCLE 14, REVISION 0, CHANGE NO. I REPLACEMENT PAGES (4 pages)

Replace the following pages of the Waterford 3 Core Operating Limits Report with the attached pages. The revised pages are identified by Revision Number 0, Change Number 1 in the bottom footer and contain vertical lines indicating the areas changed.

Remove Insert 2 2 5 5 35 35

ENTERGY OPERATIONS WATERFORD 3 CORE OPERATING LIMITS REPORT FOR CYCLE 14 REVISION 0, CHG 1 Prepared by: N. Pazooki Itv, /1/2o0'1 Nuclear Engineering Reviewed by: P.M. Melancon/R.L. Williams

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. cen,,ing -Sk 0L.1 J. B. Holman 0. q9 j Approved by:

.. - )clear Engineering Approved by: R.J. Murillo

/ Licen sing WATERFORD 3 Page 1 CYCLE 14 REVISION 0, CHG 1

WATERFORD 3 CORE OPERATING LIMITS REPORT CYCLE 14, REVISION 0, CHG 1 INDEX PAGE I. INTRODUCTION 5 II. AFFECTED TECHNICAL SPECIFICATIONS 6 3.1.1.1 Shutdown Margin - Any CEA Withdrawn COLR 3/4 1-1 3.1.1.2 Shutdown Margin - All CEAs Fully Inserted COLR 3/4 1-3 3.1.1.3 Moderator Temperature Coefficient COLR 3/4 1-4 3.1.2.9 Boron Dilution COLR 3/4 1-15 3.1.3.1 Movable Control Assemblies - CEA Position COLR 3/4 1-18 3.1.3.6 Regulating and Group P CEA Insertion Limits COLR 3/4 1-25 3.2.1 Linear Heat Rate COLR 3/4 2-1 3.2.3 Azimuthal Power Tilt - Tq COLR 3/4 2-4 3.2.4 DNBR Margin COLR 3/4 2-6 3.2.7 Axial Shape Index COLR 3/4 2-12 3.9.1 Boron Concentration COLR 3/4 9-1 III. METHODOLOGIES 34 LIST OF EFFECTIVE PAGES Revision 0 Pages 1-6, COLR 3/4 1-1 through COLR 3/4 9-1 and Pages 34 through 35 Revision 0, CHG 1 Pages 1, 2, 5, 35 WATERFORD 3 Page 2 CYCLE 14 REVISION 0, CHG 1 1

WATERFORD 3 CORE OPERATING LIMITS REPORT CYCLE 14, REVISION 0, CHG 1

1. INTRODUCTION This CORE OPERATING LIMITS REPORT (COLR) has been prepared in accordance with the requirements of Waterford 3 Technical Specification 6.9.1.11 for Waterford 3 Cycle 14. The core operating limits have been developed using the NRC approved methodologies specified in Section III. This is Revision 0 of the Cycle 14 COLR.

The major changes between the Cycle 14 Revision 0 COLR and the Cycle 13 COLR are listed below:

• The Table of Contents List of Effective Pages was updated.

• The List of Figures was revised to add COLR Figure 9A and to update the List of Effective Figure Pages

• This Introduction section was revised to reflect the changes for Cycle 14.

• Figure 2 was changed to limit the most-negative hot full power MTC to less negative than -3.9 x 10-4 Ap/ OF.

" Section 3.2.1 was revised to list the Linear Heat Rate with COLSS in service as 12.9 kw/ft and the Linear Heat Rate with COLSS out of service as 13.2 kw/ft.

• Figure 6 represents the Linear Heat Rate for Cycle 14 of 12.9 kw/ft and constant with temperature with COLSS in Service

• Figure 7 represents the Linear Heat Rate for Cycle 14 of 13.2 kw/ft and constant with temperature with COLSS Out of Service

• Section 3.2.4.c was revised to allow use of Figure 9A

• Notes below the text of Section 3.2.4 for use with Figures 8, 8A, 9 & 9A were updated and new notes were added.

• Figure 8, was revised to incorporate cycle-specific limits for Cycle 14.

• Figure 8A, was revised to provide better resolution for the four power ranges in the lower portion of Figure 8.

• Figure 9, was revised to incorporate cycle-specific limits for Cycle 14.

• Figure 9A, was added to provide better resolution for the four power ranges in the lower portion of Figure 9.

" Section 3.2.7 was revised to incorporate the new Axial Shape Index (ASI) limits required to support extended power uprate and the Cycle 14 COOS analysis.

• Section 111.6 was revised to correct the document number.

• Sections 111.9 and 111.10 were added in accordance with License Amendment 199, Extended Power Uprate.

• Sections 111.11,111.12 and 111.13 were added in accordance with License Amendment to modify TS 6.9.1.11.1, Core Operating Limits Report. These methodologies were added to support eventual adoption of Zirconium Diboride as an integral fuel burnable absorber and ZIRLOTM fuel rod cladding.

The change between the Cycle 14 Revision 0 COLR and the Cycle 14 Revision 0 Chg. 1 COLR is listed below:

• Section 111.14, was added in accordance with License Amendment 210 to reference topical report WCAP-16072-P-A. This methodology supports the use of Zirconium Diboride (ZrB2) burnable absorber coating on fuel pellets.

WATERFORD 3 Page 5 CYCLE 14 REVISION 0, CHG 1

9. "Technical Description Manual for the CENTS Code," WCAP-15996-P-A, April 2004. (Methodology for Specification 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.1 for Movable Control Assemblies - CEA Position, 3.1.3.6 for Regulating and group P CEA Insertion Limits, and 3.2.3 for Azimuthal Power Tilt).

10. "Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model," CENPD-1 32, Supplement 4-P-A, March 2001. (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt and 3.2.7 for ASI).

11. "Implementation of ZIRLO Material Cladding in CE Nuclear Power Fuel Assembly Designs," CENPD-404-P-A, November 2001. (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).

12. "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," WCAP-1 1596-P-A, June 1988; "ANC: A Westinghouse Advanced Nodal Computer Code," WCAP-10965-P-A, September 1986; and "ANC: A Westinghouse Advanced Nodal Computer Code: Enhancements to ANC Rod Power Recovery," WCAP-1 0965-P-A Addendum 1, April 1989. (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.6 for Regulating and group P CEA Insertion Limits, 3.1.2.9 Boron Dilution (Calculation of CBC and IBW), and 3.9.1 Boron Concentration).

13. "Qualification of the Two-Dimensional Transport Code PARAGON," WCAP-16045-P-A, August 2004. (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.6 for Regulating and group P CEA Insertion Limits, 3.1.2.9 Boron Dilution (Calculation of CBC & IBW), and 3.9.1 Boron Concentration).

14. "Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs," WCAP-16072-P-A (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).

WATERFORD 3 Page 35 CYCLE 14 REVISION 0, CHG 1