L-2014-091, Cycle 21 Core Operating Limits Report

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Cycle 21 Core Operating Limits Report
ML14094A010
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 03/28/2014
From: Katzman E
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2014-091
Download: ML14094A010 (19)
v • d • e


Text

March 28, 2014 L-2014-091 a

10 CFR 50.36 PPL.

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 2 Docket No. 50-389 Cycle 21 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 21.

Technical Specification 6.9.1.1 l.d requires that the COLR, including any mid-cycle revisions or supplements, be provided to the NRC upon issuance for each reload cycle. Accordingly, attached is a copy of the St. Lucie Unit 2, Cycle 21 Core OperatingLimits Report, Revision 0.

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

Very truly yours, Eric S. Katzman Licensing Manager St. Lucie Plant ESK/KWF Attachment - "St. Lucie Unit 2, Cycle 21 Core Operating Limits Report"

ý\00L Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957

L-2014-091 Attachment ST. LUCIE UNIT 2, CYCLE 21 CORE OPERATING LIMITS REPORT Revision 0 St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 1 of 18--------------------

St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 1 of 18

L-2014-091 Attachment 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 OF 5 2.9 SHUTDOWN MARGIN - Tavg Less Than or Equal To 200 OF 5 3.0 List of Approved Methods 14 List of Tables and Figures Title Page Table 3.2-2 DNB Margin Limits 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 FrT 8 Fig 3.1-2 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 FrT 12 Fig 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER 13

2--Cycle-----21-----------Re

-- t.-----ucie Unit ---- 0--Page----

---.--- 2--of-- St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 2 of 18

L-2014-091 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 Parameters, Refueling Operations - Boron Concentration, SHUTDOWN MARGIN - Tavg 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. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 3 of 18

L-2014-091 Attachment 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/0 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. < 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 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 Monitorinq System, the AXIAL SHAPE INDEX shall be maintained within the limits of Figure 3.2-2.

Cycle specific W(z) curves to be used in the linear heat rate verification, to account for power distribution transients, are shown in Table 3.2-3 as function of core height for various cycle burnups. For other cycle burnups, W(z) values may be interpolated or extrapolated as needed.

If the 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. Linear heat rate margin decreases 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 in the W(z) function of Table 3.2-3.

St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 4 of 18

L-2014-091 Attachment Incore Detector Monitoring System During operation, with the linear heat rate being monitored by the Incore Detector Monitorinq 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 - Fm (TS 3.2.3)

The calculated value of FrT shall be limited to < 1.60.

The power dependent FrT 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 Keff of 0.95 or less, or
b. A boron concentration of greater than or equal to 1900 ppm.

2.8 SHUTDOWN MARGIN - Tav. 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 - Tan 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 21 COLR Rev. 0 Page 5 of 18

L-2014-091 Attachment Table 3.2-2 DNB MARGIN LIMITS PARAMETER FOUR REACTOR COOLANT PUMPS OPERATING Cold Leg Temperature (narrow Range) 5350 F** < T _<551°F 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 >_70% of RATED THERMAL POWER.

St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 6 of 18----------------------

St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 6 of 18

L-2014-091 Attachment COLR Table 3.2 W(z) Factors as a Function of Core Height Core Height 100 EFPH 2000 EFPH 4000 EFPH 7000 EFPH 10000 EFPH (ft) (145 MWD/MTU) (2903 MWD/MTU- (5805 MWD/MTU) (10159 MWD/MTU) (14513 MWD/MTUI

<1.59* 1 1 1 1 1 1.75 1.309 1.274 1.249 1.307 1.375 1.91 1.296 1.263 1.237 1.297 1.316 2.07 1.283 1.252 1.226 1.285 1.294 2.23 1.269 1.240 1.214 1.273 1.270 2.39 1.256 1.228 1.202 1.259 1.251 2.55 1.245 1.218 1.193 1.246 1.236 2.71 1.236 1.209 1.186 1.232 1.223 2.86 1.226 1.202 1.179 1.220 1.210 3.02 1.216 1.195 1.173 1.211 1.201 3.18 1.207 1.189 1.169 1.206 1.197 3.34 1.199 1.184 1.166 1.200 1.195 3.50 1.194 1.177 1.162 1.194 1.192 3.66 1.190 1.170 1.157 1.189 1.190 3.82 1.185 1.165 1.151 1.183 1.187 3.98 1.179 1.160 1.146 1.177 1.183 4.14 1.173 1.156 1.141 1.170 1.178 4.30 1.166 1.150 1.137 1.162 1.173 4.46 1.159 1.145 1.132 1.154 1.168 4.62 1.151 1.139 1.127 1.145 1.161 4.77 1.143 1.132 1.122 1.136 1.154 4.93 1.135 1.125 1.117 1.127 1.147 5.09 1.126 1.118 1.111 1.118 1.141 5.25 1.116 1.110 1.104 1.110 1.135 5.41 1.108 1.103 1.099 1.103 1.133 5.57 1.102 1.099 1.097 1.101 1.140 5.73 1.102 1.102 1.098 1.103 1.153 5.89 1.106 1.109 1.102 1.110 1.170 6.05 1.113 1.115 1.106 1.121 1.186 6.21 1.121 1.120 1.120 1.132 1.202 6.37 1.126 1.128 1.138 1.142 1.216 6.52 1.131 1.145 1.156 1.151 1.229 6.68 1.142 1.161 1.173 1.161 1.241 6.84 1.158 1.176 1.190 1.171 1.252 7.00 1.172 1.190 1.206 1.182 1.261 7.16 1.185 1.204 1.222 1.192 1.269 7.32 1.197 1.217 1.236 1.201 1.275 7.48 1.209 1.229 1.249 1.209 1.279 7.64 1.220 1.239 1.262 1.216 1.282 7.80 1.230 1.249 1.272 1.222 1.282 7.96 1.239 1.257 1.282 1.227 1.281 8.12 1.247 1.265 1.291 1.233 1.279 8.28 1.253 1.273 1.300 1.243 1.276 8.43 1.260 1.279 1.307 1.258 1.271 8.59 1.264 1.288 1.311 1.273 1.274 8.75 1.269 1.297 1.318 1.285 1.294 8.91 1.284 1.306 1.338 1.298 1.311 9.07 1.300 1.324 1.366 1.314 1.324 9.23 1.315 1.351 1.395 1.333 1.339 9.39 1.337 1.378 1.423 1.350 1.359 9.55 1.363 1 1.403 1.449 1 1.367 1.381 9.71 1.386 1 1.427 1.474 1 1.385 1.401

>9.86 1 1 1 1 1 I op dUBotomI I0-/o aIr e*lIUUeU.

"/rW The above W(z) values are applicable to Full Power conditions. For Part Power application, divide these values by the power fraction or, alternately, divide the measured LHR by the power fraction.

St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 7 of 18------------------------

St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 7 of 18

L-2014-091 Attachment 1.62 (63,1.60) 1.60 I

  • P P P P P P P P P P 1.58-L-

-a 1.56-CU) 1.54-1.52-a) 1.50-1.48-1.46-1.44-0 5 10 15202530354045 50 55 60 65 70 75 Time at Full Power to Realign CEA, Minutes FIGURE 3.1-1a Allowable Time to Realign CEA vs. Initial FrT St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 8 of 18

L-2014-091 Attachment C ~ '

U 1,: 0 LU 0.90 Cý aCL gn 0 C,6=

- j 00 :1 (0 W 0.80 E I l L 0.80  % 0 0 0.60 I INETINN 0 0.20--

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0.10 ~ILN EM~ISOTTR LiI I STT I INSR IOL IMI I o Group No. 5 31 (136) (108.8) (81.6) (54.4) (27.2) (0) (136) (108.8) (81.6) (54.4) (27.2) (0) (136) (108.8) (81.6) (5.) (27.2) (0) 4 2 Group No. I I I I I I I I I 1 1 (136) (108.8) (81.6) (54.4) (27.2) (0) (136) (108.8) (81.6) (54.4) (27.2) (0)

CEA GROUP POSITION

-- - -I-- - -I--- -- - -- - - I-- - - I--- -I- I- (INCHES I--

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WITHDRAWN) -I--- - I--

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FIGURE 3.1-2 CEA Group Insertion Limits vs. THERMAL POWER St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 9 of 18

L-2014-091 Attachment 14.0 13.5 UNACCEPTABLE OPERATION U 13.0

-I-'

CU12.5 CU (U

n 12.0 ACCEPTABLE OPERATION U) 3:

0 11.5 11.0 I I BOL Cycle Ufe EOL (Fuel + Clad + Moderator)

FIGURE 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 10 of 18--------------------

St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 10 of 18

L-2014-091 Attachment 1.10

-6NACCEPTAB*E OPERATION REGION 1.00  :(-0.8,1.0) (0.08,10) 7 - - - - --------- . . . .. .... . - -

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0.40

-0.7 -0.5 -0.3 -0.1 0.1 0.3 0.5 0.7 Peripheral AXIAL SHAPE INDEX (Not Applicable Below 40% Power)

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 21 COLR Rev. 0 Page 11 of 18

L-2014-091 Attachment

i.. .. .

*----! UNACCEPTABLE *. ------ .. .! ' i '

--- A -- --- N--- C ------------

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-"~~~ - -, - - -r-- - - -, . -..T - - -,. .,- -- v'-T- -r - ---- - - - - r- .- -r - . . - - - -- -- *-

44 ------- --. OPERATION-o- .  : .. -.---- - ------- "..------ - -

S....--- - ---- ---- -- '.--- '(1.60, 1.0)--------- --- :------ -------------------------------- -------

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(1) rA:  : FrT LIMIT CURVE _ L_ :_--- --- --- -- -- ----------- --4 ------

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FrT 1.60"[1i+i0.4"(1 -FP) I

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0. --- . ." . ""FGRE 3.2-3

. -, - - - - - T - - -r . . . . . . - - - - - --

0 . 1 1.5 1. 1.6 1. 1.7 1 Measured FrT FIGURE 3.2-3 Allowable Combinations of THERMAL POWER and FrT (The expression specified in the Figure may be used for FrJ at other power levels)

St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 12 of 18

L-2014-091 Attachment 1.10

(-0.08,1.00) (0.15,1.00) 1.00 UNACCEPTABLE: UNACCEPtABLE OPERATION OPERATION:

REGION REGIN 0ý 0.90 0~ --- -- - ------

0- ---- -- ---

0.80 --------

_-_-ý- ACCEPTABLE-ul OPERATION uJ 0.70

(-0.50,0.65) - ------------ (0.50,0.65)-- - -

0 0.60

.4-'

0 CU U-0.50 0.40

-0.7 -0.5 -0.3 -0.1 0.1 0.3 0.5 0.7 Peripheral AXIAL SHAPE INDEX (Y1)

(Not Applicable Below 40% Power)

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 21 COLR Rev. 0 Page 13 of 18

L-2014-091 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. 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, April 1999
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-1 6 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 21 COLR Rev. 0 Page 14 of 18----------------------

St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 14 of 18

L-2014-091 Attachment

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(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. CEN PD-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-II, 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
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. CEN PD-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-137, 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 St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 15 of 18

L-2014-091 Attachment

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-1 6 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)

Lucie--Unit--2-Cycle--21--------Re---0--Page t.------------------

of-- -18

-16 St. Lucie Unit 2 Cycle 21 COILR Rev. 0 Page 16 of 18

L-2014-091 Attachment

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-1 37, 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 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 (USNRC), "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," April 1999.

St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 17 of 18

L-2014-091 Attachment

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 1975.
68. WCAP-7588, Rev. 1-A, "An Evaluation of the Rod Ejection Accident in Westinghouse Pressurized Water Reactors Using Spatial Kinetics Methods," January 1975 St. Lucie Unit 2 Cycle 21 COLR Rev. 0 Page 18 of 18
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