L-2006-128, Cycle 16 Core Operating Limits Report

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Cycle 16 Core Operating Limits Report
ML061510347
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 05/25/2006
From: Johnston G
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2006-128
Download: ML061510347 (19)
v • d • e


Text

F i Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 May 25, 2006 FPL L-2006-128 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 16 Core Operating Limits Report Pursuant to St. Lucie Unit 2 Technical Specification (TS) 6.9.1.1 l.d, Florida Power & Light Company (FPL) is submitting the Core Operating Limits Report (COLR) for operating cycle 16.

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 16 Core Operating Limits Report, Revision 0.

Please contact us ifthere are any questions regarding this submittal.

Very truly yours, Gordon L. Johnston Acting Vice Pres;iden St. Lucie Plant GLJ/spt Attachment an FPL Group company A40ol

r St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment ST. LUCIE UNIT 2, CYCLE 16 CORE OPERATING LIMITS REPORT Revision 0 111e106 Verified By V/XIO ATroved BY St. Lucie Unit 2 Cycle 16 COLR Rev 0 Page I of 18

St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment Table of Contents Description Page 1.0 Introduction 3 2.0 Core Operating Umits 2.1 Moderator Temperature Coefficient 4 2.2 CEA Position - Misalignment > 15 inches 4 2.3 Regulating CEA Insertion Umits 4 2.4 Unear Heat Rate 4 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR 5 2.6 DNB Parameters - AXIAL SHAPE INDEX 5 2.7 Refueling Operations - Boron Concentration 5 2.8 SHUTDOWN MARGIN - T.,, Greater Than 200 OF 5 2.9 SHUTDOWN MARGIN - T,,, Less Than or Equal To 200 OF 5 3.0 Ust of Approved Methods 14 List of Tables and Figures Title P&g_

Table 3.2-2 DNB Margin Umits 6 Table 3.2-3 W(z) Factors as a Function of Core Height 7 Fig 3.1-1a Allowable Time To Realign CEA vs. Initial FT 8 Fig 3.1-2 CEA Insertion Limits vs. THERMAL POWER 9 Fig 3.2-1 Allowable Peak Unear 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 FT 12 Fig 3.2-4 AXIAL SHAPE INDEX Operating ULmits vs. THERMAL POWER 13 Rev 0 Page 2 of 18 St. Lucie St. 2 Cycle Unit 2 Lucle UnIt 16 COLR Cycle 16 COLR Rev 0 Page 2 of 18

St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment

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 INTEGRATED RADIAL PEAKING FACTOR - FrT DNB Parameter Refueling Operations - Boron Concentration SHUTDOWN MARGIN - T,, Greater Than 200 OF 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. Lucle Unit 2 Cycle 16 COLR Rev 0 Page 3 of 18

f St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment 2.0 CORE OPERATING UMITS 2.1 Moderator Temperature Coefficient (TS 3.1.1.4)

The moderator temperature coefficient (MTC) shall be less negative than -32 pcnm/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 InFigure 3.1-1a.

2.3 Reaulatina 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 Umits and the Power Dependent Insertion Umits 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.

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.

Cycle specific W(z) curves to be used Inthe linear heat rate verification, to account for power distribution transients, are shown in Table 32-3 as function of core height for various cycle bumups. For other cycle bumups, W(z) values may be Interpolated or extrapolated as needed.

Ifthe margin to the linear heat rate has decreased as determined from the last two flux maps, then the linear heat rate must be increased by an appropriate penalty. A value of 2% Is chosen as the standard penalty. Unear heat rate margin decreases St. Lucle Unft 2 Cycle 16 COLR Rev 0 Page 4 of 18

St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment that are predicted to be greater than 2% per 31 Effective Full Power Days require that penalty factors of greater than 2% be used to increase the measured linear heat rate LHRm(z). The Incremental penalty factors (in excess of 2% margin decrease) are included Inthe W(z) function of Table 3.2-3.

Incore Detector Monitoring System 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.

2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR - F.1 (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 (TS 3.2.6)

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. Reactor Coolant System Flow rate
d. 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 K0f of 0.95 or less, or
b. A boron concentration of greater than or equal to 1720 ppm.

2.8 SHUTDOWN MARGIN -LT~v* Greater Than 200 OF (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 OF (TS 3.1.1.2)

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

Rev 0 PageSof 18 St. UnIt 22 Cycle Lucie Unit St. Lucie 16 COLR Cycle 16 COLR Rev 0 Page 5 of 18

St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment Table 3.2-2 DNB MARGIN LIMITS PARAMETER FOUR REACTOR COOLANT pUMPS OPERATING Cold Leg Temperature (narrow Range) 535OF** _<T < 5490F Pressurizer Pressure* 2225 psia < Ppn < 2350 psia**

Reactor Coolant Flow Rate >:335,000 gpm 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% of RATED THERMAL POWER or aTHERMAL POWER step increase of greater than 10% of RATED THERMAL POWER.

    • Applicable only if power level > 70% of RATED THERMAL POWER.

Rev 0 Page6oIl8 St.

SL Lucie Unit 2 Lucle UnIt 2 Cycle 16 COLR Cycle 16 COLR Rev 0 Page 6 of 18

St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment COLR Table 3.2-3 W(z) Factors as a Function of Core Height for St Lucle Unit 2 Cycle 16 w(-)

Core Height 100 EFPH 2000 EFPH 5000 EFPH 8000 EFPH 10000 EFPH (ft) (130 MWD/MTU) (2598 MWMT (6494 MWDIrrU) (10391 MWDJMTU) ,(12988 MWD/MTU) 1I.59 *1.000 1.000 1.000 1.000 1.000 1.75 1.293 1.272 1.270 1.301 1.357 1.91 1.282 1.262 1.260 1.290 1.328 2.07 1270 1251 1.249 1.279 1.306 2.23 1.259 1.240 1.238 1.267 1.285 2.89 1.247 1.231 1.227 1.255 1.262 2.55 1.235 1.222 1.214 1.241 1.244 2.70 1.226 1.214 1.201 1.228 1.232 2.8 1.219 1.208 1.189 1.214 1.223 8.02 1.212 1.204 1.179 1.206 1.217 3.18 1.205 1.199 1.173 1.20M 1.212 8.34 1.199 1.193 1.171 1.200 1.206 3.50 1.192 1.188 1.170 1.197 1.201 3.66 1.185 1.183 1.168 1.193 1.194 8.82 1.180 1.178 1.185 1.189 1.186 3.98 1.175 1.174 1.162 1.184 1.180 4.14 1.170 1.168 1.158 1.178 1.178 4.30 1.164 1.162 1 1.154 1.172 1.174 4.45 1.158 1.155 1.149 1.165 1.169 4.61 1.151 1.148 1.143 1.157 1.164 4.77 1.144 1.140 1.187 1.149 1.168 4". 1.137 1.132 1.131 1.141 1.182 5.09 1,129 1.124 1.125 1.132 1.144 5.25 1.120 1.115 1.117 1.122 1.138 5.41 1.112 1.109 1.111 1.116 1.137 5.57 1.107 1.107 1.112 1.116 1.141 5.73 1.108 1.109 1.113 1.124 1.151 5.89 1.114 1.114 1.121 1.136 1.165 6.05 1.119 1.120 1.137 1.147 1.179 6.20 1.123 1.128 1.152 1.158 1.192 6.88 1.131 1.138 .1.166 1.168 1.204 6.52 1.144 1.148 1.180 1.178 1.215 6.63 1.158 1.159 1.194 1.183 1.226 6.84 1.172 1.170 1.208 1.199 1.236 7.00 1.185 1.182 1 .223 1 0 1.245 7.16 1.198 1.194 1.352 1.219 1.295 7.02 1.210 1.2D4 1.251 1.228 1.310 7.48 I "1 1214 1-254 1.20 1282 ...

7.64 1.230 1,223 1.275 1.243 1.264 7.30 1.870 1.231 1.284 12*95 1.848 1252 1.85 1.2)"

7.95 1.247 i.29 MI51 1.252 1.244 1.392 1.254 1,263 9.27 L.43 1.257 1.2B4 1249 1.257 1.308 1.314 1.256 1.265 139 1.264 8.5O 1.270 1.2"M 1.M2 1.2 1269 8.51.2"78 1,287 1.835 1I.29 1.280 8.91 1293 1.310 1 .=5 1.319 1.295 9.07 1.316 1*2 1.871 1.M3 1-310 9.23 1.344 1.353 1.390 1.356 1,327 s.8 1.87 I=7 1.414 1 ,1.84 1.348 9.65 1M35 1.391 1.A39 1.413 1.370 9.70 1 A19 1.408 1.462 1.436 1.389

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St. Lucle Unit 2 Cycle 16 COLR Rev 0 Page 7 of 18

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FIGURE 3.1-2 CEA Group Insertion Limits vs. THERMAL POWER Page 9 of 18 St. Lucle UnIt 22 Cycle Lucie Unit Cycle 16 16 COLR COLR Rev 0 Rev 0 Page 9 of 18

St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment 14.0-a a 1:3.5 . --

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FIGURE 3.2-1 Allowable Peak Linear Heat Rate vs. Bumnup St. Lucle Unit 2 Cycle 16 COLR Rev 0 Page 10 of 18

St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment 1.10 *

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St Lucle Unit 2 Cycle 16 COLR Rev 0 Page ll of 18

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St. Lucle Unit 2 Cycle 16 COLR Rev 0 Page 12 of 18

St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment 1.10 1.00 W

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(AXIAL SHAPE INDEX limits for DNB)

SL Lucie Unit 2 Cycle 16 COLR Rev 0 Page 13 of I a

St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment 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-1 1596-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-1 99-P, Rev. 1-P-A, "C-E Setpoint Methodology:. CE Local Power Density and DNB LSSS and LCO Setpolnt 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," May1988, &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-1 53-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.

Lucle Unit 1,0 December 1979

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

Combination of System Parameter Uncertainties inThermal 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 Unear Heat Rate Limiting Conditions for Operation for St. Lucle 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 16 COLR Rev 0 Page 14 of IS

St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment

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-1 23(F)-P (three parts) and CEN-1 91 (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

'3/4.2.5 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 Distdbution," 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-Il, a Program for Emergency Refill-Reflood of the Core," June 1985
26. CENPD-135-P, Supplement 5, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977 St. Lucie Unit 2 Cycle 16 COLR Rev 0 Page 15 of 18

St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment

27. Letter, R. L. Baer (NRC) to A. E. Scherer (CE), "Evaluation of Topical Report CENPD-1 35, 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, AComputer 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. Bohike (FPL) to Document Control Desk (NRC), "St. Lucie Unit 2, Docket No. 50-389, Proposed Ucense Amendment, MTC Change from -27 pcm to -

30 pj," 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. Elsenhut (NRC), "St. Lucie Unit No. 2, Docket No. 50-389, Proposed Ucense 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 Rev 0 0 Page 16 of 18 St. Lucie St. UnIt 22 Cycle Lucie Unit 16 COIR Cycle 16 COLR Rev Page 16 of 18

St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment

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, uExtended Statistical Combination of Uncertainties,n 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-1 99-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 Bumup Umit 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 Bumup Operation of Combustion Engineering PWR Fuel," July 1984
60. CEN-289(A)-P, "Revised Rod Bow Penalties for Arkansas Nuclear One Unit 2,"

December 1984 (NRC SER dated December21, 1999, Letter K.N.Jabbour (NRC) to T. F. Plunkert (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 Analysts," June 1988 (NRC SER dated March 13, 1989, Letter J. A.

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

St. Lucie Unft 2 Cycle 16 COLR Rev 0 Page 17 of 18

St. Lucie Unit 2 Docket No. 50-389 L-2006-128 Attachment

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

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. CENPD-404-P-A, Rev. 0, 'Implementation of ZIRLOTm Cladding Material in CE Nuclear Power Fuel Assembly Designs," November 2001
59. WCAP-9272-P-A, *Westinghouse Reload Safety Evaluation Methodology'" July 1985
60. WCAP-10216-P-A, Revision lA, "Relaxation of Constant Axial Offset Control; FQ Surveillance Technical Specification," February 1994
61. WCAP-1 1397-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 I 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 (USNRC), "St. Lucie Unit 2 Docket No. 50-389: Proposed License Amendment WCAP-9272 Reload Methodology and Implementing 30% Steam Generator Tube Plugging Umit,* L-2003-276, December, 2003 (NRC SER dated January 31, 2005, Letter B. T. Moroney (NRC) to J. A.Stall (FPL), TAC No. MCI 566)

St Lucle Unit 2 Cycle 16 COLR Rev 0 page 18 Of I a

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