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Rev 1 to PCM 99016, St Lucie Unit 1,Cycle 16 Colr.
	ML17241A474
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Site:	Saint Lucie
Issue date:	08/31/1999
From:	; FLORIDA POWER & LIGHT CO.
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	PCM-99016, PCM-99016-R01, NUDOCS 9910060167
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PCM No. 99016 Rev1 Attachment 14, Page 1 of 14 ST. LUCIE UNIT 1, CYCLE 16 CORE OPERATING LIMITS REPORT Revision 1 Prepared By: s/~~Je~

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PCM No. 99016 Rev1 Attachment 14, Page 2 of 14 Table of Contents Descri tion ~Pa e 1.0 Introduction 2.0 Core Operating Limits 2.1 Moderator Temperature Coefficient 2.2 Full Length CEA Position - Misalignment > 15 inches 2.3 Regulating CEA Insertion Limits 2.4 Linear Heat Rate 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR 2.6 DNB Parameters - AXIALSHAPE INDEX 2.7 Refueling Operations - Boron Concentration 3.0 List of Approved Methods 12 List of Figures

~Fi Ure Title ~Pa e 3.1-1a Allowable Time To Realign CEA vs. Initial F, '

3.1-2 CEA Insertion Limits vs. THERMAL POWER 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup 3.2 2 AXIALSHAPE INDEX vs. Maximum Allowable Power Level 3.2 3 Allowable Combinations of THERMAL POWER and F, 10 3.2-4 AXIALSHAPE INDEX Operating Limits vs. THERMAL POWER St. Lucie Unit1 Cycle 16 COLR Rev1 Page 2 of14

PCM No. 99016 Rev1 Attachment 14, Page 3 of 14

1.0 INTRODUCTION

This CORE OPERATING LIMITS REPORT (COLR) describes the cycle-specific parameter limits for operation of St. Lucie Unit 1 Cycle 16. 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 RADIALPEAKING FACTOR - F, DNB Parameter - AXIALSHAPE INDEX Refueling Operations - Boron Concentration 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.

St. Lucie Unit 1 Cycle 16 COLR Rev 1 Page 3 of 14

PCM No. 99016 Rev 1 Attachment 14, Page 4 of 14 2.0 CORE OPERATING LIMITS 2.1 Moderator Tem erature Coefficient (TS 3.1.1.4)

The moderator temperature coefficient (MTC) shall be less negative than -32 pcmf'F at RATED THERMALPOWER.

2.2 Full Len th CEA Position - Misali nment > 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 3.1-1a.

2.3 Re ulatin 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 AXIALSHAPE 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 Monitorin S stem, the AXIALSHAPE 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 Monitorin S stem, 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 1 Cycle 16 COLR Rev1 Page4 of14

PCM No. 99016 Rev1 Attachment 14, Page 5 of 14 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR Fr (TS 3.2.3)

The calculated value of F, shall be limited to < 1.70.

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

2.6 DNB Parameters - AXIALSHAPE INDEX (TS 3.2.5)

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

2.7 Refuelin 0 erations - 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 K,g 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.

St. Lucie Unit 1 Cycle 16 COLR Rev1 Page5 of14

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St. Lucie Unit 1 Cycle 16 COLR Rev1 Page 11 of 14

PCM No. 99016 Rev 1 Attachment 14, Page 12 of 14 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.

WCAP-11596-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 1 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 1 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 1 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. a) ANF-84-93(P)(A) and Supplement 1, [also issued as XN-NF-84-93(P)(A)],

"Steamline Break Methodology for PWRs," Advanced Nuclear Fuels Corporation, March 1989 b) EMF-84-093(P)(A) Revision 1, "Steam Line 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. Siemens Small Break LOCA methodology as defined by:

a) XN-NF-82-49(P)(A) Revision 1, "Exxon Nuclear Company Evaluation Model EXEM PWR Small Break Model," Advanced Nuclear Fuels Corporation, April 1989 St. Lucie Unit 1 Cycle 16 COLR Rev 1 Page12 of14

PCM No. 99016 Rev1 Attachment 14, Page 13 of 14 b) 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. EXEM PWR Large Break LOCA Evaluation Model as defined by:

a) 1. XN-NF-82-20(P)(A) Revision 1 Supplement 2, "Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates," Exxon Nuclear Company, Inc., February 1985

2. XN-NF-82-20(P)(A) Revision 1 and Supplements 1, 3 and 4, "Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates,"

Advanced Nuclear Fuels Corporation, January 1990

3. XN-NF-82-20(P)(A) Revision 1 Supplement 6, "EXEM/PWR Large Break LOCA ECCS Model Updates," Siemens Power Corporation, June 1998 b) XN-NF-82-07(P)(A) Revision 1, "Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, Inc., November 1982 c) 1. XN-NF-81-58(P)(A) Revision 2, and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, Inc., March 1984

2. ANF-81-58(P)(A) Revision 2 Supplement 3, and Supplement 4, "RODEX2 Fuel Rod Thermal Mechanical Response Evaluation Model," Advanced Nuclear Fuels Corporation, June 1990 d) XN-NF-85-16(P)(A) Volume 1, and Supplements 1, 2 and 3; Volume 2, Revision 1 and Supplement 1, "PWR 17x17 Fuel Cooling Test Program," Advanced Nuclear Fuels Corporation, February 1990 e) XN-NF-85-105(P)(A) and Supplement 1, "Scaling of FCTF Based Ref lood Heat Transfer Correlation for Other Bundle Designs," Advanced Nuclear Fuels Corporation, January 1990 f) EMF-2087(P)(A) Revision 0, "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, June 1999 St. Lucie Unit 1 Cycle 16 COLR Rev1 Page13 of 14

PCM No. 99016 Rev1 Attachment 14, Page 14 of 14

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

13. ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels'WR 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. XN-NF-507(P)(A), Supplements 1 and 2, "ENC Setpoint Methodology for C. E.

Reactors: Statistical Setpoint Methodology," Exxon Nuclear Company, Inc.,

September 1986 St. Lucie Unit1 Cycle16 COLR Rev1 Page 14 of 14

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ML17241A474: Difference between revisions

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