Text

Cycle 24 Core Operating Limits Report
	ML18255A328
Person / Time
Site:	Saint Lucie
Issue date:	09/12/2018
From:	Snyder M; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2018-167
	Download: ML18255A328 (20)
	v • d • e

SEP 1 2 2018 L-2018-167 10 CFR50.36 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 2 Docket No. 50-389 Cycle 24 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 24.

Technical Specification 6.9.1.11.d requires that the COLR, including any mid-cycle rev1s1ons or supplements, be provided to the NRC upon issuance for each reload cycle. Accordingly, attached is a copy of the St. Lucie Unit 2, ycle 24 Core Operating Limits &port, Revision 0.

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

Michael J. Snyder Licensing Manager St. Lucie Plant MJS/KWF Attachment- "St. Lucie Unit 2, Cycle 24 Core Operating Limits Report" cc: USNRC Regional Administrator, Region II USNRC Senior Resident Inspector, St. Lucie Nuclear Plant Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957

L-2018-167 Page 1 of 19 ST. LUCIE UNIT 2, CYCLE 24 CORE OPERATING LIMITS REPORT Revision 0 St. lucie Unit 2 Cycle 24 COLR Rev. 0 Page 1 of 19

L-2018-167 Page 2 of 19 Table of Contents Description Page 1.0 Introduction 3 2.0 Core Operating Limits 4 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 INTEGRATED RADIAL PEAKING FACTOR 5 2.6 DNB Parameters 5 2.7 Refueling Operations - Boron Concentration 5 2.8 SHUTDOWN MARGIN- Tavg Greater Than 200 °F 5 2.9 SHUTDOWN MARGIN- Tavg Less Than or Equal To 200 °F 5 3.0 List of Approved Methods 14 List of Tables and Figures Table 3.2-2 DNB Margin Limits 6 Table 3.2-3 Nolongerused 7 Fig3.1-1a Allowable Time To Realign CEA vs. Initial Frr 8 Fig3.1-2 CEA Group Insertion Limits vs. THERMAL POWER 9 Fig 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup 10 Fig 3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level 11 Fig 3.2-3 Allowable Combinations of THERMAL POWER and Frr 12 Fig 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER 13 St. Lucie Unit 2 Cycle 24 COLR Rev.O Page 2 of 19

L-2018-167 Page 3 of 19

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.

~v~oderator Temperature Coefficient, CEA Position- Misalignment> 15 Inches, Regulating CEA Insertion Limits, Linear Heat Rate, TOTAL INTEGRATED RADIAL PEAKING FACTOR- Frr DNB Parameters, Refueling Operations - Boron Concentration, SHUTDOWN MARGIN- Tavg Greater Than 200 °F, SHUTDOWN MARGIN- Tavg Less Than or Equal To 200 °F.

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 24 COLR Rev.O Page 3 of 19

L-2018-167 Page 4 of 19 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 3.1-1 a.

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 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 Days, 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.

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

lncore Detector Monitoring System During operation, with the linear heat rate being monitored by the lncore 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 2 Cycle 24 COLR Rev.O Page 4 of 19

L-2018-167 Page 5 of 19 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR- Fl (TS 3.2.3)

The calculated value of Frr shall be limited to.:::_ 1.60.

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

2.6 DNB Parameters (TS 3.2.5)

The following DNB-related parameters shall be maintained within the limits shown on Table 3.2-2:

a. Cold Leg Temperature

b. Pressurizer Pressure

c. AXIAL SHAPE INDEX 2.7 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 Ken of 0.95 or less, or

b. A boron concentration of greater than or equal to 1900 ppm.

2.8 SHUTDOWN MARGIN- Tavg Greater Than 200 °F (TS 3.1.1.1)

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

2.9 SHUTDOWN MARGIN- Tavg Less Than or Equal To 200 °F (TS 3.1.1.2)

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

St. Lucie Unit 2 Cycle 24 COLR Rev.O Page 5 of 19

L-2018-167 Page 6 of 19 Table 3.2-2 DNB MARGIN LIMITS PARAMETER FOUR REACTOR COOLANT PUMPS OPERATING Cold Leg Temperature (narrow Range)

Pressurizer Pressure* 2225 psia :::; PPzR :::; 2350 psia**

AXIAL SHAPE INDEX Within the limits specified in Figure 3.2-4 Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% per minute of RATED THERMAL POWER or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER.

Applicable only if power level :2: 70% of RATED THERMAL POWER.

St. Lucie Unit 2 Cycle 24 COLR Rev.O Page 6 of 19

L-2018-167 Page 7 of 19 Table 3.2 No longer used St. Lucie Unit 2 Cycle 24 COLR Rev.O Page 7 of 19

L-2018-167 Page 8 of 19

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FIGURE 3.1-2 CEA Group Insertion Limits vs. THERMAL POWER St. Lucie Unit 2 Cycle 24 COLR Rev.O Page 9 of 19

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FIGURE 3.2-1 Allowable Peak Linear Heat Rate vs. Burn up St. Lucie Unit 2 Cycle 24 COLR Rev.O Page 10 of 19

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FIGURE 3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level Note: AXIAL SHAPE INDEX limits for Linear Heat Rate when using Excore Detector Monitoring System St. Lucie Unit 2 Cycle 24 COLR Rev.O Page 11 of 19

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(The expression specified in the Figure may be used for F/ at other power levels)

St. Lucie Unit 2 Cycle 24 COLR Rev.O Page 12 of 19

L-2018-167 Page 13 of 19 1.10

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FIGURE 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER (Four Reactor Coolant Pumps Operating)

(AXIAL SHAPE INDEX limits for DNB)

St. Lucie Unit 2 Cycle 24 COLR Rev.O Page 13 of 19

L-2018-167 Page 14 of 19 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. Deleted.

4. Deleted.

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, April1999

6. Deleted.

7. Deleted.

8. CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 1: CE Calculated Local Power Density and Thermal Margin/Low Pressure LSSS for St.

Lucie Unit 1," December 1979

9. Deleted.

10. CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 3: CE Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for St. Lucie Unit 1," February 1980

11. CEN-191 (B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2," December 1981

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-16 and SER), November 9, 1984 (Approval of CEN-123(F)-P (three parts) and CEN-191 (B)-P)

13. Deleted.

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

'3/4.2.5 DNB Parameters' (TAC No. M87722)," March 14, 1994 (Approval of CEN-371 (F)-P)

St. Lucie Unit 2 Cycle 24 COLR Rev.O Page 14 of 19

L-2018-167 Page 15 of 19

15. Deleted.

16. Deleted.

17. Deleted.

18. Deleted.

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 (8)-P-A, "Improvements to Fuel Evaluation Model," August 1989

22. CEN-161(8)-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 FORTRAN?? Digital Computer Program for Reactor Slowdown 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-11, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977

27. Letter, R. L. Baer (NRC) to A. E. Scherer (CE), "Evaluation of Topical Report CENPD-135, Supplement #5," September 6, 1978

28. CENPD-137, Supplement 1-P, "Calculative Methods for the C-E Small Break LOCA Evaluation Model," January 1977

29. CENPD-133, Supplement 3-P, "CEFLASH-4AS, A Computer Program for the Reactor Slowdown 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-137, Supplement 1-P," September 27, 1977

31. CENPD-138, 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 St. Lucie Unit 2 Cycle 24 COLR Rev.O Page 15 of 19

L-2018-167 Page 16 of 19

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. \AJ. VVi!!iams, 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. Deleted.

38. Deleted.

39. Deleted.

40. Deleted.

41. Deleted.

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. Deleted.

45. Deleted.

46. Deleted.

47. Deleted.

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)

St. Lucie Unit 2 Cycle 24 COLR Rev.O Page 16 of 19

L-2018-167 Page 17 of 19

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. Deleted.

54. Deleted.

55. CENPD-387 -P-A, Revision 000, "ABB Critical Heat Flux Correlations for PWR Fuel,"

May 2000

56. CENPD-132, Supplement 4-P-A, "Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model," March 2001

57. CENPD-137, Supplement 2-P-A, "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model," April 1998

58. WCAP-12610-P-A & CENPD-404-P-A, Addendum 2-A, "Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLO," October 2013.

59. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology"' July 1985

60. WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control; FQ Surveillance Technical Specification," February 1994

61. WCAP-11397 -P-A, (Proprietary), "Revised Thermal Design Procedure," April 1989

62. WCAP-14565-P-A, (Proprietary), "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis," October 1999

63. WCAP-14565-P-A, Addendum 1-A, Revision 0, "Addendum 1 to WCAP-14565-P-A Qualification of ABB Critical Heat Flux Correlations with VIPRE-01 Code," August 2004

64. Letter, W. Jefferson, Jr. (FPL) to Document Control Desk (US NRC), "St. Lucie Unit 2 Docket No. 50-389: Proposed License Amendment WCAP-9272 Reload Methodology and Implementing 30% Steam Generator Tube Plugging Limit," L-2003-276, December, 2003 (NRC SER dated January 31, 2005, Letter B. T. Moroney (NRC) to J. A. Stall (FPL), TAC No. MC1566)

65. WCAP-14882-P-A, Rev. 0, "RETRAN-02 Modeling and Qualification for Westinghouse Pressurized Water Reactor Non-LOCA Safety Analyses," April1999.

St. Lucie Unit 2 Cycle 24 COLR Rev.O Page 17 of 19

L-2018-167 Page 18 of 19

66. WCAP-7908-A, Rev. 0, "FACTRAN-A FORTRAN IV Code for Thermal Transients in a U02 Fuel Rod," December 1989.

67. WCAP-7979-P-A, Rev. 0, "TWINKLE - A Multi-Dimensional Neutron Kinetics Computer Code," January 197 5.

68. WCAP-7588, Rev. 1-A, "An Evaluation of the Rod Ejection Accident in Westinghouse Pressurized Water Reactors Using Spatial Kinetics Methods," January 1975.

69. WCAP-16045-P-A, Revision 0, "Qualification of the Two-Dimensional Transport Code PARAGON," August 2004.

70. EMF-96-029(P)(A), Volumes 1 and 2, "Reactor Analysis System for PWRs, Volume 1 Methodology Description, Volume 2 Benchmarking Results," Siemens Power Corporation, January 1997.

71. 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.

72. XN-75-27(A) and Supplements 1 through 5, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors," Exxon Nuclear Company, Report and Supplement 1 dated April1977, Supplement 2 dated December 1980, Supplement 3 dated September 1981 (P), Supplement 4 dated December 1986 (P), and Supplement 5 dated February 1987 (P).

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

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L-2018-167, Cycle 24 Core Operating Limits Report

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L-2018-167, Cycle 24 Core Operating Limits Report

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