L-2004-138, Cycle 19 Core Operating Limits Report - Revision 1

Cycle 19 Core Operating Limits Report - Revision 1

ML041900252
Person / Time
Site:	Saint Lucie
Issue date:	06/29/2004
From:	Jefferson W Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2004-138
Download: ML041900252 (14)

Text

Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 June 29, 2004 FPL L-2004-1 38 10 CFR 50.36 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Ld'ie Unit 1 Docket No. 50-335 Cycle 19 Core Operating Limits Report - Revision 1 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 I for operating cycle 19.

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.

This revision to the COLR makes the cycle 19 COLR consistent with the recently approved License Amendment 191. Accordingly, attached is a copy of the St. Lucie Unit 1, Cycle 19 Core Operating Limits Report, Revision 1.

William Jfef~ec Vice President St. Lucie Plant WJ/spt Attachment 0I an FPL Group company

St. Lucie Unit I Docket No. 50-335 L-2004-138 Attachment ST. LUCME; UNIT 1, CYCLE 19 CORE O.-=P.ATING LIMITS REPORT PRevision I Prepareb byj:

t- :nak-Verified E':

Approved ,

St. Lucie Unit 1 Docket No. 50-335 L-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 4 2.3 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 5 2.8 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 6 3.1-2 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 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 1 Page2 of 13 St. Lucie St. Unit 1 Lucle Unit 1 Cycle 19 COLR Cycle 19 COLR Rev I Page 2 of 13

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

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 - 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 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.

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

St. Lucie Unit I Docket No. 50-335 L-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 -32 pcm/ 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 length CEA 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 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.

Ut 1__e Lce1g St.._ - o St. Lucie Unit 1 Cycle 19 COLR Rev I Page 4 of 13

St. Lucie Unit I Docket No. 50-335 L-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 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 mot:

a. Either a Kff 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-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

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Page7 of 13 Cyclo 19 Unit I1 Cycle Lucle Unit St. Lucie 19 COLR COLR Rev 11 Rev Page 7 of 13

St Lucie Unit I Docket No. 50-335 L-2004-138 Attachment 17.0 A-S UNACCEPTABLE OPERATION 16.0 6

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FIGURE 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup Rev 1 Page 8 of 13 St. Lucie Unit I1 Cycle Lucle Unit 19 COIR Cycle 19 COLR Rev 1 Page 8 of 13

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

4 -

St. Lucia Unit 1 Docket No. 50-335 L-2004-138 Attachment 3.0 LIST OF APPROVED METHODS The analytical methods used to dstermine 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-PIANC 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)J, OExoon Nuclear Neutronic(s) Design Methods for Pressurized Water Reactors,"

Exxon Nuclear Company, Inc. I Advanced Nuclear Fuels Corporation, Report and Supplement 1dated 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. 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-7844(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, 'SEMIPWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, June 1999 St. Lucie Unit 1 Cycle 19 COLR Rev 1 Page 12 of 13

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

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

14. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dloxide/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, OHTP: Departure from Nucleate Boiling Correlation 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 Volume 1- Methodology Description, Volume 2- Benchmarking Results,- Siemens Power Corporation, January 1997

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

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

22. EMF-2328(P)(A), Revision 0, "PWR Small Break LOCA Evaluation Model, S-RE LAPS Based," March 2001 Rev I Page 13 ofl3 St.

SL Lucie Cycle 19 Unit II Cycle Lucle Unit COIR 1 9 COLR Rev I Page 13 of 13