L-2003-110, Cycle 14 Core Operating Limits Report

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Cycle 14 Core Operating Limits Report
ML031250044
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 05/01/2003
From: Jefferson W
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2003-110
Download: ML031250044 (17)
v • d • e


Text

'I ; Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 FPL May 1,2003 L-2003-1 10 10 CFR 50.36 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 2 Docket No. 50-389 Cycle 14 Core Operating Limits Report Pursuant to St. Lucie Unit 2 Technical Specification (TS) 6.9.1.11.d, Florida Power & Light Company (FPL) is submitting the Core Operating Limits Report (COLR) for operating cycle 14.

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 2, Cycle 14 Core Operating Limits Report, Revision 0.

Please contact us if there are any questions regarding this submittal.

Vice President St. Lucie Plant WJ/spt Attachment IVYZ an FPL Group company

St. Lucie Unit 2 Docket No. 50-389 L-2003-1 10 Attachment Page 1 PCM 02142 Rev. 0 Attachment 14, Page 1 of 16 ST. LUCIE UNIT 2, CYCLE 14 CORE OPERATING LIMITS REPORT Revision 0

' fepared By

./

Verified By Approved By St. Lucie Unit 2 Cycle 14 COLR Rev 0 Page 1 of 16

St. Lucie Unit 2 Docket No. 50-389 L-2003-1 10 Attachment Page 2 PCM 02142 Rev. 0 Attachment 14, Page 2 of 16 Table of Contents Description Page 1.0 Introduction 3 2.0 Core Operating Limits 2.1 Moderator Temperature Coefficient 4 2.2 CEA Position - Misalignment > 15 inches 4 2.3 Regulating CEA Insertion Limits 4 2.4 Linear Heat Rate 4 2.5 TOTAL PLANAR RADIAL PEAKING FACTORS 5 2.6 TOTAL INTEGRATED RADIAL PEAKING FACTOR 5 2.7 DNB Parameters - AXIAL SHAPE INDEX 5 2.8 Refueling Operations - Boron Concentration 5 2.9 SHUTDOWN MARGIN - Tavg Greater Than 200 0F 5 2.10 SHUTDOWN MARGIN - Tavg Less Than or Equal To 200 OF 5 3.0 List of Approved Methods 12 List of Figures Figure Title Page 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. Burnup 8 3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level 9 3.2-3 Allowable Combinations of THERMAL POWER and FT, Fx1T 10 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER 11 St. L Unit 2 Cycle 14 C

_cie _LR Rev Page

_ 2 _116 St. Lucie Unit 2 Cycle 14 COLR Rev 0 Page 2 of 16

St. Lucie Unit 2 Docket No. 50-389 L-2003-1 10 Attachment Page 3 PCM 02142 Rev. 0 Attachment 14, Page 3 of 16

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) describes the cycle-specific parameter limits for operation of St. Lucie Unit 2. It contains the limits for the following as provided in Section 2.

Moderator Temperature Coefficient CEA Position - Misalignment > 15 Inches Regulating CEA Insertion Limits Linear Heat Rate TOTAL PLANAR RADIAL PEAKING FACTORS - F,'7 TOTAL INTEGRATED RADIAL PEAKING FACTOR - FrT DNB Parameter - AXIAL SHAPE INDEX Refueling Operations - Boron Concentration SHUTDOWN MARGIN - Tavg Greater Than 200 F SHUTDOWN MARGIN - Tavg 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.

St. Lucie Unit 2 Cycle 14 COLR Rev 0 Page 3 of 16

St. Lucie Unit 2 Docket No. 50-389 L-2003-1 10 Attachment Page 4 PCM 02142 Rev. 0 Attachment 14, Page 4 of 16 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 CEA Position - Misalignment > 15 Inches (TS 3.1.3.1)

The time constraints for full power operation with one full-length CEA misaligned from any other CEA in its group by more than 15 inches 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. Less than or equal to 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. Less than or equal to 5 Effective Full Power Days per 30 Effective Full Power Days, and
c. Less than or equal to 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. L Unit 2 Cycle 14 L Rev 0 Page 4_o 1 _

St. Lucie Unit 2 Cycle 14 COLR Rev 0 Page4 of 16

St. Lucie Unit 2 Docket No. 50-389 L-2003-1 10 Attachment Page 5 PCM 02142 Rev. 0 Attachment 14, Page 5 of 16 1

2.5 TOTAL PLANAR RADIAL PEAKING FACTORS - F, (TS 3.2.2)

The calculated value of F T shall be limited to < 1.75.

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

2.6 TOTAL INTEGRATED RADIAL PEAKING FACTOR - Fj (TS 3.2.3)

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

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

2.7 DNB Parameters - AXIAL SHAPE INDEX (TS 3.2.5)

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

2.8 Refueling Operations - Boron Concentration (TS 3.9.1)

With the reactor vessel head closure bolts less than fully tensioned or with the head removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal 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, or
b. A boron concentration of greater than or equal to 1720 ppm.

2.9 SHUTDOWN MARGIN - Tavn Greater Than 200 OF (TS 3.1.1.1)

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

2.10 SHUTDOWN MARGIN - Tav, Less Than or Equal To 200 OF (TS 3.1.1.2)

The SHUTDOWN MARGIN shall be greater than or equal to 3000 pcm.

St. Lucie Unit 2 Cycle 14 COLR Rev 0 Page 5 of 16

St. Lucie Unit 2 Docket No. 50-389 L-2003-1 10 Attachment Page 6 PCM 02142 Rev. 0 Attachment 14, Page 6 of 16 1.72 I I 70I 1.70

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St. Lucie Unit 2 Cycle 14 COLR Rev O Page80of 16

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St. Lucie Unit 2 Cycle 14 COLR Rev 0 Page 90of16

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St. Lucie Unit 2 Cycle 14 COLR Rev O Page 11 of 16

St. Lucie Unit 2 Docket No. 50-389 L-2003-1 10 Attachment Page 12 PCM 02142 Rev. 0 Attachment 14, Page 12 of 16 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-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 (NRC SER dated June 9,1995), & Supplement 1, August 1997

3. CENPD-199-P, Rev. 1-P-A, UC-E Setpoint Methodology: CE Local Power Density and DNB LSSS and LCO Setpoint Methodology for Analog Protection Systems," January 1986
4. CENPD-266-P-A, 'The ROCS and DIT Computer Code for Nuclear Design," April 1983
5. CENPD-275-P, Revision 1-P-A, C-E Methodology for Core Designs Containing Gadolinia-Urania Burnable Absorbers," May 1988, & Revision 1-P Supplement 1-P-A, April 1999
6. CENPD-188-A, "HERMITE: A Multi-Dimensional Space - Time Kinetics Code for PWR Transients," July 1976
7. CENPD-153-P, Rev. 1-P-A, "Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System," May 1980
8. CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin/Low Pressure LSSS for St.

Lucie Unit 1," December 1979

9. CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 2:

Combination of System Parameter Uncertainties in Thermal Margin Analyses for St.

Lucie Unit 1," January 1980

10. CEN-123(F)-P, *Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for St. Lucie Unit 1," February 1980
11. CEN-1 91 (B)-P, 'CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2," December 1981 St. Lucie Unit 2 Cycle 14 COLR Rev 0 Page 12 of 16

St. Lucie Unit 2 Docket No. 50-389 L-2003-1 10 Attachment Page 13 PCM 02142 Rev. 0 Attachment 14, Page 13 of 16

12. Letter, J. W. Miller (NRC) to J. R.Williams, Jr. (FPL), Docket No. 50-389, Regarding Unit 2 Cycle 2 License Approval (Amendment No. 8 to NPF-1 6 and SER), November 9, 1984 (Approval of CEN-123(F)-P (three parts) and CEN-191(B)-P)
13. CEN-371 (F)-P, "Extended Statistical Combination of Uncertainties," July 1989
14. Letter, J. A. Norris (NRC) to J. H. Goldberg (FPL), Docket No. 50-389, "St. Lucie Unit 2 - Change to Technical Specification Bases Sections '2.1.1 Reactor Core' and

'314.2.5 DNB Parameters' (TAC No. M87722)," March 14, 1994 (Approval of CEN-371 (F)-P)

15. CENPD-161-P-A, "TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986
16. CENPD-162-P-A, *Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 1, Uniform Axial Power Distribution," April 1975
17. CENPD-207-P-A, "Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 2, Non-uniform Axial Power Distribution," December 1984
18. CENPD-206-P-A, 'TORC Code, Verification and Simplified Modeling Methods," June 1981
19. CENPD-225-P-A, "Fuel and Poison Rod Bowing," June 1983
20. CENPD-139-P-A, "C-E Fuel Evaluation Model Topical Report," July 1974
21. CEN-161(B)-P-A, "Improvements to Fuel Evaluation Model," August 1989
22. CEN-161(B)-P, Supplement 1-P-A, "Improvements to Fuel Evaluation Model,"

January 1992

23. CENPD-132, Supplement 3-P-A, 'Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS," June 1985
24. CENPD-133, Supplement 5-A, "CEFLASH-4A, A FORTRAN77 Digital Computer Program for Reactor Blowdown Analysis," June 1985
25. CENPD-134, Supplement 2-A, "COMPERC-11, a Program for Emergency Refill-Reflood of the Core," June 1985
26. CENPD-135-P, Supplement 5, "STRIKIN-Il, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977 St. _ucle Unit 2 Cycle 14 _OLR Rev 0 _ Page 13_of16 St. Lucie Unit 2 Cycle 14 COLR Rev 0 Page 13 of 16

St. Lucie Unit 2 Docket No. 50-389 L-2003-110 Attachment Page 14 PCM 02142 Rev. 0 Attachment 14, Page 14 of 16

27. Letter, R. L. Baer (NRC) to A. E. Scherer (CE), 'Evaluation of Topical Report CENPD-135, Supplement #5," September 6, 1978
28. CENPD-1 37, Supplement 1-P, 'Calculative Methods for the C-E Small Break LOCA Evaluation Model," January 1977
29. CENPD-1 33, Supplement 3-P, "CEFLASH-4AS, A Computer Program for the Reactor Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977
30. Letter, K. Kniel (NRC) to A. E. Scherer (CE), "Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-1 37, Supplement 1-P." September 27, 1977
31. CENPD-1 38, Supplement 2-P, "PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup," January 1977
32. Letter, C. Aniel (NRC) to A. E. Scherer (CE), "Evaluation of Topical Report CENPD-138, Supplement 2-P." April 10, 1978
33. Letter, W. H. Bohlke (FPL) to Document Control Desk (NRC), "St. Lucie Unit 2, Docket No. 50-389, Proposed License Amendment, MTC Change from -27 Pcm to

-30 pcm," L-91-325, December 17,1991

34. Letter, J. A. Norris (NRC) to J. H. Goldberg (FPL), "St. Lucie Unit 2 - Issuance of Amendment Re: Moderator Temperature Coefficient (TAC No. M82517)," July 15, 1992
35. Letter, J. W. Williams, Jr. (FPL) to D. G. Eisenhut (NRC), "St. Lucie Unit No. 2, Docket No. 50-389, Proposed License Amendment, Cycle 2 Reload," L-84-148, June 4,1984
36. Letter, J. R. Miller (NRC) to J. W. Williams, Jr. (FPL), Docket No. 50-389, Regarding Unit 2 Cycle 2 License Approval (Amendment No. 8 to NPF-16 and SER), November 9, 1984 (Approval of Methodology contained in L-84-148)
37. Letter, A. E. Scherer Enclosure 1-P to LD-82-001, 'CESEC-Digital Simulation of a Combustion Engineering Nuclear Steam Supply System," December 1981
38. Safety Evaluation Report, "CESEC Digital Simulation of a Combustion Engineering Steam Supply System (TAC No.: 01142)," October 27,1983
39. CENPD-282-P-A, Volumes 1, 2, and 3, and Supplement 1, "Technical Manual for the CENTS Code," February 1991, February 1991, October 1991, and June 1993, respectively St_ Lc-e U_-t 2 Cycle _v 14 C_ _ Page 14 of 16___

St. Lucie Unit 2 Cycle 14 COLR Rev 0 Page 14 of 16

St. Lucie Unit 2 Docket No. 50-389 L-2003-1 10 Attachment Page 15 PCM 02142 Rev. 0 Attachment 14, Page 15 of 16

40. CEN-121(B)-P, "CEAW, Method of Analyzing Sequential Control Element Assembly Group Withdrawal Event for Analog Protected Systems," November 1979 (NRC SER dated December 21, 1999, Letter K. N. Jabbour (NRC) to T. F. Plunkett (FPL), TAC No. MA4523)
41. CEN-133(B), "FIESTA, A One Dimensional, Two Group Space-Time Kinetics Code for Calculating PWR Scram Reactivities," November 1979 (NRC SER dated December 21, 1999, Letter K. N. Jabbour (NRC) to T. F. Plunkett (FPL), TAC No.

MA4523)

42. CEN-348(B)-P-A, Supplement 1-P-A, 'Extended Statistical Combination of Uncertainties," January 1997
43. CEN-372-P-A, "Fuel Rod Maximum Allowable Gas Pressure," May 1990
44. CENPD-1 83-A, "C-E Methods for Loss of Flow Analysis," June 1984
45. CENPD-1 90-A, 'C-E Method for Control Element Assembly Ejection Analysis," July 1976
46. CENPD-199-P, Rev. 1-P-A, Supplement 2-P-A, 'CE Setpoint Methodology", June 1998
47. CENPD-382-P-A, "Methodology for Core Designs Containing Erbium Burnable Absorbers," August 1993
48. CEN-396(L)-P, 'Verification of the Acceptability of a 1-Pin Burnup Limit of 60 MWD/KG for St. Lucie Unit 2," November 1989 (NRC SER dated October 18, 1991, Letter J. A. Norris (NRC) to J. H. Goldberg (FPL), TAC No. 75947)
49. CENPD-269-P, Rev. 1-P, "Extended Burnup Operation of Combustion Engineering PWR Fuel," July 1984
50. CEN-289(A)-P, "Revised Rod Bow Penalties for Arkansas Nuclear One Unit 2,"

December 1984 (NRC SER dated December 21,1999, Letter K. N. Jabbour (NRC) to T. F. Plunkett (FPL), TAC No. MA4523)

51. CENPD-137, Supplement 2-P-A, "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model," April 1998
52. CENPD-140-A, "Description of the CONTRANS Digital Computer Code for Containment Pressure and Temperature Transient Analysis," June 1976
53. CEN-365(L), -Boric Acid Concentration Reduction Effort, Technical Bases and Operational Analysis," June 1988 (NRC SER dated March 13, 1989, Letter J. A.

Norris (NRC) to W. F. Conway (FPL), TAC No. 69325)

St. Lu__e Unit 2 Cycle_ 14 C__R__ Rev Page 15 of_

St. Lucie Unit 2 Cycle 14 COLR Rev 0 Page 15 of 16

I -

St. Lucie Unit 2 Docket No. 50-389 L-2003-110 Attachment Page 16 PCM 02142 Rev. 0 Attachment 14, Page 16 of 16

54. DP-456, F. M. Stem (CE) to E. Case (NRC), dated August 19, 1974, Appendix 6B to CESSAR System 80 PSAR (NRC SER, NUREG-75/112, Docket No. STN 50-470, "NRC SER - Standard Reference System, CESSAR System 80," December 1975)
55. CENPD-387-P-A, Revision 000, "ABB Critical Heat Flux Correlations for PWR Fuel,"

May 2000 St. Lucie Unit 2 Cycle 14 COLR Rev 0 Page 16 of 16

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