FPL

Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957

June 29, 2004

L-2004-1 3810 CFR 50.36

U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555

Re: St. Ld'ie Unit 1Docket No. 50-335Cycle 19 Core Operating Limits Report - Revision 1

Pursuant to St. Lucie Unit 1 Technical Specification (TS) 6.9.1.11 .d, Florida Power & LightCompany (FPL) is submitting the Core Operating Limits Report (COLR) Revision I foroperating cycle 19.

Technical Specification 6.9.1.11.d requires that the COLR, including any mid-cyclerevisions or supplements, be provided to the NRC upon issuance for each reload cycle.This revision to the COLR makes the cycle 19 COLR consistent with the recently approvedLicense Amendment 191. Accordingly, attached is a copy of the St. Lucie Unit 1, Cycle19 Core Operating Limits Report, Revision 1.

William Jfef~ecVice PresidentSt. Lucie Plant

WJ/spt

Attachment

0I

an FPL Group company

St. Lucie Unit IDocket No. 50-335L-2004-138 Attachment

ST. LUCME; UNIT 1, CYCLE 19

CORE O.-=P.ATING LIMITS REPORT

PRevision I

Prepareb byj:

Verified E':

t- :nak-

Approved ,

St. Lucie Unit 1Docket No. 50-335L-2004-138 Attachment

Table of Contents

Descrintion Page

1.0 Introduction 3

2.0 Core Operating limits

2.1 Moderator Temperature Coefficient 4

2.2 Full Length CEA Position - Misalignment > 15 inches 42.3 Regulating CEA Insertion Limits 4

2.4 Linear Heat Rate 4

2.5 TOTAL INTEGRAT ED RADIAL PEAKING FACTOR 5

2.6 DNB Parameters - AXIAL SHAPE INDEX 5

2.7 Refueling Operations - Boron Concentration 52.8 SHUTDOWN MARGIN- Tvg GreaterThan 200 OF 5

2.9 SHUTDOWN MARGIN -T,5, Less Than or Equal To 200 0F 5

3.0 List of Approved Methods 12

List of Figures

Figure Title Pane

3.1-1a Allovwable Time To Realign CEA vs. Initial FT 63.1-2 CEA Insertion Limits vs. THERMAL POWER 7

3.2-1 Allowable Peak linear Heat Rate vs. Burnup 8

3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level 93.2-3 Allowable Combinations of THERMAL POWER and FT 10

3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER 11

St. Lucle Unit 1 Cycle 19 COLR Rev 1 Page2 of 13St. Lucie Unit 1 Cycle 19 COLR Rev I Page 2 of 13

St. Lucie Unit 1Docket No. 50-335L-2004-1 38 Attachment

1.0 INTRODUCTION

This CORE OPERATING LIMITS REPORT (COLR) describes the cycle-specific parameterlimits for the operation of St. Lucie Unit 1. It contains the limits for the following asprovided 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 - FrT

DNB Parameter- AXIAL SHAPE INDEX

Refueling Operations - Boron Concentration

SHUTDOWN MARGIN - Tag Greater Than 200 OF

SHUTDOWN MARGIN - Tr,, Less Than or Equal To 200 OF

This report also contains the necessary figures which give the limits for the above listedparameters.

Terms appearing in capitalized type are DEFINED TERMS as defined in Section 1.0 of theTechnical Specifications.

This report is prepared In accordance with the requirements of Technical Specification6.9.1.11.

St. Lucle Unit 1 Cycle 19 COLR Rev 1 Page3 of 13St. Lucie Unit 1 Cycle 19 CO!LR Rev 1 Page 3 of 13

St. Lucie Unit IDocket No. 50-335L-2004-138 Attachment

2.0 CORE OPERATIM!G LIMITS

2.1 Moderator TemDerature Coefficient (TS 3.1.1.A)

The moderator temperature coefficient (MTC) shall be less negative than -32pcm/2F 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 lengthCEA by 15 or more Inches from any other CEA in its group are shown In Figure 3.1-1a.

2.3 Regulating CEA Insertion Limits (TS 3.1.3.6)

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

a. < 4 hours per 24 hour 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 DetectorMonitoring System, the AXIAL SHAPE INDEX shall be maintained within the limitsof Figure 3.2-2.

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

St.._ Lce Ut 1_ _e 1g - oSt. Lucie Unit 1 Cycle 19 COLR Rev I Page 4 of 13

-

St. Lucie Unit IDocket No. 50-335L-2004-138 Attachment

2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR - For (TS 3.2.3)

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

The power dependent FT 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 Figure3.2-4.

2.7 Refueling Operations - Boron Concentration (TS 3.9.1)

With the reactor vessel head unbolted or removed, the boron concentration of allfilled portions of the Reactor Coolant System and the refueling cavity shall bemaintained uniform and sufficient to ensure that the more restrictive of the followingreactivity conditions is mot:

a. Either a Kff of 0.95 or less, which Includes a 1000 pcm conservativeallowance for uncertainties, or

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

2.8 SHUTDOWN MARGIN-LT~, GreaterThan 200 0F(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 Eaual To 200 cF (TS 3.1.1.2)

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

St. Lucle Unit 1 Cycle 19 COLR Rev I Page5 of 13

St. Lucie Unit 1Docket No. 50-335L-2004-138 Attachment

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FIGURE 3.1-laAllowable Time to Realign CEA vs. Initial FT

St. Lucle Unit 1 Cycle 19 COLR Rev I Page6 of 13

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FIGURE 3.1-2CEA Insertion Limits vs. THERMAL POWER

(4 Reactor Coolant Pumps Operating)

St. Lucle Unit 1 Cyclo 19 COLR Rev 1 Page7 of 13

St. Lucie Unit I Cycle 19 COLR Rev 1 Page 7 of 13

St Lucie Unit IDocket No. 50-335L-2004-138 Attachment

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St. Lucle Unit 1 Cycle 19 COIR Rev 1 Page 8 of 13St. Lucie Unit I Cycle 19 COLR Rev 1 Page 8 of 13

St. Lucie Unit 1Docket No. 5D-335L-2004-138 Attachment

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FIGURE 3.2-2AXIAL SHAPE INDEX vs. Maximum Allowable Power Level

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St. Lucle Unit 1 Cycle 19 COLR Rev I Page9 of 13St Lucie Unit 1 Cycle 19 COLR Rev 1 Page 9 of 13

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St. Lucie Unit I Cycle 19 COLR Rev I Page 10 of 13

St. Lucia Unit I Cycle 19 COLR Rev I Page 10 of 13

St. Lucie Unit IDocket No. 5G-335L-2004-138 Attachment

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St. Lucle Unit 1 Cycle 19 COLR Rev I Page I11 of 13

4 -

St. Lucia Unit 1Docket No. 50-335L-2004-138 Attachment

3.0 LIST OF APPROVED METHODS

The analytical methods used to dstermine the core operating limits are those previouslyapproved by the NRC, and are listed below.

1. WCAP-1 1596-P-A, 'Qualification of the PHOENIX-PIANC Nuclear Design Systemfor 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)J,OExoon Nuclear Neutronic(s) Design Methods for Pressurized Water Reactors,"Exxon Nuclear Company, Inc. I Advanced Nuclear Fuels Corporation, Report andSupplement 1 dated April 1977, Supplement 2 dated December 1980, Supplement3 dated September 1981 (P), Supplement 4 dated December 1986 (P), andSupplement 5 dated February 1987 (P)

4. ANF-84-73(P)(A) Revision 5, Appendix B, & Supplements 1 and 2, 'AdvancedNuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter15 Events,' Advanced Nuclear Fuels Corporation, October 1990

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

6. EMF-84-093(P)(A) Revision 1, "Steam Une Break Methodology for PWRs," SiemensPower 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 EvaluatingFuel Rod Bowing," Exxon Nuclear Company, Inc., October 1983

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

9. XN-NF-7844(NP)(A), 'A Generic Analysis of the Control Rod Ejection Transient forPressurized Water Reactors,' Exxon Nuclear Company, Inc., October 1983

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

11. EMF-2087(P)(A) Revision 0, 'SEMIPWR-98: ECCS Evaluation Model for PWRLBLOCA Applications," Siemens Power Corporation, June 1999

St. Lucie Unit 1 Cycle 19 COLR Rev 1 Page 12 of 13

St. Lucie Unit IDocket No. 50-335L-2004-1 38 Attachment

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

13. ANF-88133(P)(A) and Supplement 1, Qualification of Advanced Nuclear Fuels'PWR Design Methodology for Rod Burnups of 62 GWdIMTU," Advanced NuclearFuels Corporation, December 1991

14. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dloxide/Gadolinia IrradiationExamination 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 FuelDesign," Siemens Power Corporation, February 1999

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

19. EMF-96-029(P)(A) Volumes 1 and 2, TReactor Analysis System for PWRs Volume1 - Methodology Description, Volume 2 - Benchmarking Results,- Siemens PowerCorporation, January 1997

20. EMF-1961(P)(A), Revision 0, "Statistical Setpoint/rransient Methodology forCombustion Engineering Type Reactors," Siemens Power Corporation, July 2000

21. EMF-2310(P)(A), Revisikn 1, "SRP Chapter 15 Non-LOCA Methodology forPressurized Water Reactors," May 2004

22. EMF-2328(P)(A), Revision 0, "PWR Small Break LOCA Evaluation Model, S-RE LAPSBased," March 2001

St. Lucle Unit I Cycle 19 COIR Rev I Page 13 ofl3SL Lucie Unit I Cycle 1 9 COLR Rev I Page 13 of 13