L-2002-209, Cycle 18 Core Operating Limits Report - Revision 0

Cycle 18 Core Operating Limits Report - Revision 0

ML023030212
Person / Time
Site:	Saint Lucie
Issue date:	10/18/2002
From:	Jernigan D Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2002-209
Download: ML023030212 (14)

Text

0FPL Florida Power & Light Company. 6501 South Ocean Drive, Jensen Beach, FL 34957 October 18, 2002 L-2002-209 10 CFR 50.36 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Cycle 18 Core Operating Limits Report - Revision 0 Pursuant to St. Lucie Unit 1 Technical Specification (TS) 6.9.1.11.d, Florida Power &

Light Company (FPL) is submitting the Core Operating Limits Report (COLR) Revision 0 for operating cycle 18.

Technical Specification 6.9.1.11.d requires that the COLR, including any mid-cycle revisions or supplements, be provided to the NRC upon issuance for each reload cycle.

Accordingly, enclosed is a copy of the St. Lucie Unit 1, Cycle 18 Core Operating Limits Report, Revision 0.

Please/ 0 tact George Madden at 772-467-7155 if there are any questions about this subnptt" ryry tr y yours, Donal (

Donald E.J e a*an Vice President St. Lucie Plant DEJ/GRM Enclosure 0

an FPL Group company

St. Lucie Unit 1 Docket No. 50-335 L-2002-209 Enclosure PC/M No. 02014 Rev 0 Attachment 14, Page 1 of 13 ST. LUCIE UNIT 1, CYCLE 18 CORE OPERATING LIMITS REPORT Revision 0 Prepared By: a ci Verified By:

Approved By:

St. Lucie Unit 1 Docket No. 50-335 L-2002-209 Enclosure PC/M No. 02014 Rev 0 Attachment 14, Page 2 of 13 Table of Contents Description Paqe 1.0 Introduction 3 2.0 Core Operating Limits 2.1 Moderator Temperature Coefficient 4 2.2 Full Length CEA Position - Misalignment > 15 inches 4 2.3 Regulating CEA Insertion Limits 4 2.4 Linear Heat Rate 4 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR 5 2.6 DNB Parameters - AXIAL SHAPE INDEX 5 2.7 Refueling Operations - Boron Concentration 5 2.8 SHUTDOWN MARGIN - T,,, Greater Than 200 OF 5 2.9 SHUTDOWN MARGIN - T,,g Less Than or Equal To 200 OF 5 3.0 List of Approved Methods 12 List of Figures Figure Title PEg 3.1-1a Allowable Time To Realign CEA vs. Initial FrT 6 3.1-2 CEA Insertion Limits vs. THERMAL POWER 7 3.2-1 Allowable Peak Linear Heat Rate vs. Bumup 8 3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level 9 3.2-3 Allowable Combinations of THERMAL POWER and FT 10 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER 11 Rev 0 Page 2 ofl3 St. Lucie Unit 18 COLR Cycle 18 Unit II Cycle COLR Rev 0 Page 2 of 13

St. Lucie Unit 1 Docket No. 50-335 L-2002-209 Enclosure PC/M No. 02014 Rev 0 Attachment 14, Page 3 of 13

1.0 INTRODUCTION

This CORE OPERATING LIMITS REPORT (COLR) describes the cycle-specific parameter limits for the operation of St. Lucie Unit 1. It contains the limits for the following as provided in Section 2.

Moderator Temperature Coefficient Full Length CEA Position - Misalignment > 15 Inches Regulating CEA Insertion Limits Linear Heat Rate TOTAL INTEGRATED RADIAL PEAKING FACTOR - FT DNB Parameter - AXIAL SHAPE INDEX Refueling Operations - Boron Concentration SHUTDOWN MARGIN -T.2 Greater Than 200 OF SHUTDOWN MARGIN - Tag Less Than or Equal To 200 OF This report also contains the necessary figures which give the limits for the above listed parameters.

Terms appearing In capitalized type are DEFINED TERMS as defined in Section 1.0 of the Technical Specifications.

This report is prepared in accordance with the requirements of Technical Specification 6.9.1.11.

RevO Page 3 ofl3 St. Lucie Unit II Cycle Lucie Unit 18 COLR Cycle 18 COLR Rev 0 Page 3 of 13

St. Lucie Unit 1 Docket No. 50-335 L-2002-209 Enclosure PCIM No. 02014 Rev 0 Attachment 14, Page 4 of 13 2.0 CORE OPERATING LIMITS 2.1 Moderator Temperature Coefficient (TS 3.1.1.4)

The moderator temperature coefficient (MTC) shall be less negative than -32 pcm/°F at RATED THERMAL POWER.

2.2 Full Length CEA Position - Misalignment > 15 Inches (TS 3.1.3.1)

The time constraints for full power operation with the misalignment of one full length CEA by 15 or more inches from any other CEA in its group are shown in Figure 3.1 I a.

2.3 Regulatinq CEA Insertion Limits (TS 3.1.3.6)

The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown on Figure 3.1-2, with CEA insertion between the Long Term Steady State Insertion Limits and the Power Dependent Insertion Limits restricted to:

a. < 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval,

b. < 5 Effective Full Power Days per 30 Effective Full Power Day interval, and

c. < 14 Effective Full Power Days per calendar year.

2.4 Linear Heat Rate (TS 3.2.1)

The linear heat rate shall not exceed the limits shown on Figure 3.2-1.

The AXIAL SHAPE INDEX power dependent control limits are shown on Figure 3.2 2.

During operation, with the linear heat rate being monitored by the Excore Detector Monitoring System, the AXIAL SHAPE INDEX shall be maintained within the limits of Figure 3.2-2.

During operation, with the linear heat rate being monitored by the Incore Detector Monitoring System, the Local Power Density alarm setpoints shall be adjusted to less than or equal to the limits shown on Figure 3.2-1.

St. Lucie Unit I Cycle 18 COLR Rev 0 Page 4 of 13

St. Lucie Unit 1 Docket No. 50-335 L-2002-209 Enclosure PCIM No. 02014 Rev 0 Attachment 14, Page 5 of 13 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR - FT (TS 3.2.3)

The calculated value of FT shall be limited to < 1.70.

The power dependent Fr limits are shown on Figure 3.2-3.

2.6 DNB Parameters - AXIAL SHAPE INDEX (TS 3.2.5)

The AXIAL SHAPE INDEX shall be maintained within the limits specified in Figure 3.2-4.

2.7 Refueling Operations - Boron Concentration (TS 3.9.1)

With the reactor vessel head unbolted or removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling cavity shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:

a. Either a Keff of 0.95 or less, which includes a 1000 pcm conservative allowance for uncertainties, or

b. A boron concentration of > 1720 ppm, which includes a 50 ppm conservative allowance for uncertainties.

2.8 SHUTDOWN MARGIN - T., Greater Than 200 OF (TS 3.1.1.1)

The SHUTDOWN MARGIN shall be greater than or equal to 3600 pcm.

2.9 SHUTDOWN MARGIN -T,,, Less Than or Equal To 200 OF (TS 3.1.1.2)

The SHUTDOWN MARGIN shall be greater than or equal to 2000 pcm.

Rev 0 Page 5 of 13 St. Lucie Unit II Cycle Lucie Unit 18 COLR Cycle 18 COLR Rev 0 Page 5 of 13

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St. Lucie Unit I Cycle 18 COLR Rev 0 Page 7 of 13

St. Lucie Unit 1 Docket No. 50-335 L-2002-209 Enclosure PCIM No. 02014 Rev 0 Attachment 14, Page 8 of 13 17.0 w 16.0 UNACCEPTABLE OPERATION

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Rev 0 Pagell ofl3 St. Lucle Unit St. Lucie Cycle 18 Unit I1 Cycle 18 COLRCOLR Rev 0 Page 11 of 13

St. Lucie Unit 1 Docket No. 50-335 L-2002-209 Enclosure PCIM No. 02014 Rev 0 Attachment 14, Page 12 of 13 3.0 LIST OF APPROVED METHODS The analytical methods used to determine the core operating limits are those previously approved by the NRC, and are listed below.

1. WCAP-1 1596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988 (Westinghouse Proprietary)

2. NF-TR-95-01, "Nuclear Physics Methodology for Reload Design of Turkey Point &

St. Lucie Nuclear Plants," Florida Power & Light Company, January 1995

3. XN-75-27(A) and Supplements I through 5, [also issued as XN-NF-75-27(A)],

"Exxon Nuclear Neutronic(s) Design Methods for Pressurized Water Reactors,"

Exxon Nuclear Company, Inc. /Advanced Nuclear Fuels Corporation, Report and Supplement I dated April 1977, Supplement 2 dated December 1980, Supplement 3 dated September 1981 (P), Supplement 4 dated December 1986 (P), and Supplement 5 dated February 1987 (P)

4. ANF-84-73(P)(A) Revision 5, Appendix B, & Supplements I and 2, "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation, October 1990

5. XN-NF-82-21(P)(A) Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, Inc., September 1983

6. EMF-84-093(P)(A) Revision 1, "Steam Une Break Methodology for PWRs," Siemens Power Corporation, February 1999 (This document is a Revision to ANF-84-93)

7. XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, Inc., October 1983

8. XN-NF-82-49(P)(A) Revision 1 Supplement 1, "Exxon Nuclear Company Evaluation Model Revised EXEM PWR Small Break Model," Siemens Power Corporation, December 1994

9. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, Inc., October 1983

10. XN-NF-621(P)(A) Revision 1, "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company, Inc., September 1983

11. EMF-2087(P)(A) Revision 0, "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, June 1999 Page 12 ofl3 Lucle Unit I St. Lucie I Cycle 18 COLR Cycle 18 COLR Rev 0 Rev 0 Page 12 of 13

St. Lucie Unit 1 Docket No. 50-335 L-2002-209 Enclosure PClM No. 02014 Rev 0 Attachment 14, Page 13 of 13

12. XN-NF-82-06(P)(A) Revision 1, and Supplements 2, 4 and 5, "Qualification of Exxon Nuclear Fuel for Extended Bumup," Exxon Nuclear Company, Inc., October 1986

13. ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991

14. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, Inc.,

November 1986

15. ANF-89-151(P)(A), 'ANF-RELAP Methodology for Pressurized Water Reactors:

Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, May 1992

16. Deleted

17. EMF-92-116(P)(A), Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Design," Siemens Power Corporation, February 1999

18. EMF-92-153(P)(A) and Supplement 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, March 1994

19. EMF-96-029(P)(A) Volumes I and 2, "Reactor Analysis System for PWRs Volume I - Methodology Description, Volume 2 - Benchmarking Results," Siemens Power Corporation, January 1997

20. EMF-1961(P)(A), Revision 0, "Statistical SetpointlTransient Methodology for Combustion Engineering Type Reactors," Siemens Power Corporation, July 2000 Rev 0 Page 13 ofl3 Lucie Unit St. Lucie St. Cycle 18 Unit II Cycle COLR 18 COLR Rev 0 Page 13 of 13