ML16287A422

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FS1-0028339 Revision 1.0, Brunswick, Unit 1, Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM30 Methodology.
ML16287A422
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Site: Brunswick  Duke Energy icon.png
Issue date: 09/26/2016
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Office of Nuclear Reactor Regulation
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FS1-0028339, Rev 1.0
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BSEP 16-0078 Enclosure 8 AREVA Document FS1-0028339 Revision 1.0, Brunswick Unit 1 Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM30 Methodology (Nonproprietary Version)

IDENTIFICATION REVISION I

FS1-0028339 11 1.0 I

AREVA Front End BG Fuel BL A

AREVA TOTAL NUMBER OF PAGES: 18 Brunswick Unit 1 Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM3D Methodology (Non-Proprietary Version)

ADDITIONAL INFORMATION :

This is the Non-proprietary version of FS 1-0028338.

PROJECT DISTRIBUTION TO PURPOSE OF DISTRIBUTION HANDLING Restricted AREVA Roland DeSteese EIR - E ngineering CATEGORY Inform a tion R e port STATUS This document is electronically approved . Records regarding the signatures are stored in the Fuel BU Document Database. Any attempt to modify this file may subject employees to civil and criminal penalties. EDM Object Id: 0901216780988bbc - Release date (YYYY/MM/DD) : 2016/09/01 17:13:38 [Western European Time]

Role Name Date IYYYY/MM/DDl Oraanization Writer CROCKETT Dean 2016/08/31 23:16:41 AREVA Inc.

Writer FOWLES Robert 2016/08/31 23:08:43 AREVA Inc.

Reviewer RILEY Earl 2016/08/31 23:48 :06 AREVA Inc.

Reviewer TYUNSKI Scott 2016/09/01 00:55:51 AREVA Inc.

Approver MEGINNIS Alan 2016/09/01 01:05:46 AREVA Inc.

Approver SCHNEPP Robert 2016/09/01 17"13:31 AREVA Inc.

Exportkennzeichnun g AL : OE00 1 ECCN: OE001 RELEASE DATA: Die mit "AL ungleich N" gekennzeichneten GOter unterliegen bei der Ausfuhr aus der EU bzw.

innergemeinschaftlichen Verbringung der europc1ischen bzw. deutschen Ausfuhrgenehmigungspflicht. Die mit "ECCN ungleich N" gekennzeichneten GOter untertiegen der US-Reexportgenehmigungspflicht. Auch ohne Kennzeichen , bzw. bei Kennzeichen "AL: N" oder "ECCN: N", kann sich eine Genehmigungspflicht, unter anderem durch den Endverbleib und Verwendungszweck der GOter, ergeben.

SAFETY RELATED DOCUMENT: y Export classification AL: OE001 ECCN: OE001 Goods labeled with "AL not equ al to N" are subject to Europea n or German export authorization CHANGE CONTROL RECORDS : France: N when being exported within or out of the EU . Goods labeled with "ECCN not eq ual to N" are subject Th is document, when revised , must be USA: y to US reexport authorization. Even without a label, or with label "AL: N" or ~ E CC N : N", authorization may be req uired due to the final whereabouts and pu rpose for which the goods are to be used .

reviewed or approved by the following regions: Germany: N CW01l Rev. 4 .3 - 314/15

No FS 1-0028339 Rev. 1.0 Brunswick Unit 1 Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM3D Methodology A

Handling: Restricted AREVA Page 2/18 AREVA (Non-Proprietary Version)

REVISIONS REVISION DATE EXPLANATORY NOTES 1.0 See 151 page Initial issue.

release date This is the Non-proprietary version of FS 1-0028338.

AREVA- Fuel BL This document is sub*ect to the restrictions set forth on the first or title a e

No FS 1-0028339 Rev. 1.0 Brunswick Unit 1 Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM3D Methodology A

.AREVA Handling: Restricted AREVA Page 3/18 (Non-Proprietary Version)

Documentation of Multiple Analysts, Reviewers, or Approvers (Reference FSOP-7 Appendix 2)

Type of Review Role:

(applies to W= Pages/Sections Full Name & Title Reviewers only):

Writer/Analyst Signature Date Prepared/Reviewed (printed or typed) T =Technical R= Reviewer I Approved D = Documentation A= Approver B =Both Dean CROCKETT, w NIA-Approval of NIA All except Figures Engineer document in 1-2, Figures 4-7 electronic workflow constitutes acceptance.

Ed FOWLES, w NIA-Approval of NIA Figures 1-2, Engineer document in Figures 4-7 electronic workflow constitutes acceptance.

Scott TYLINSKI, R NIA- Approval of NIA All except Figures B Supervisor document in 1-2, Figures 4-7 electronic workflow constitutes acceptance.

Earl RILEY, R NIA- Approval of NIA Figures 1-2, B Supervisor document in Figures 4-7 electronic workflow constitutes acceptance.

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No FS 1-0028339 Rev. 1.0 Brunswick Unit 1 Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM3D Methodology A

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TABLE OF CONTENTS

1. PURPOSE .............................................................................................................................................5
2. METHODOLOGY ..................................................................................................................................5
3. ANALYSIS .............................................................................................................................................6
4. DISCUSSION OF RES ULTS .................................................................................................................7
5. REFERENCES ......................................................................................................................................8 LIST OF TABLES Table 1 Fuel- and Plant-Related Uncertainties for Brunswick SLMCPR Analyses ...................................... 9 Table 2 Results Summary for Brunswick Unit 1 Cycle 21 SLMCPR Analysis ........................................... 10 Table 3 Results Summary for Brunswick Unit 2 Cycle 23 SLMCPR Analysis ........................................... 10 Table 4 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type for Brunswick Unit 1 Cycle 21 .......................................................................................................................................11 Table 5 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type for Brunswick Unit 2 Cycle 23 .......................................................................................................................................11 LIST OF FIGURES Figure 1 Brunswick Unit 1 Cycle 21 Core Loading Map ............................................................................ 12 Figure 2 Brunswick Unit 2 Cycle 23 Core Loading Map ............................................................................ 13 Figure 3 Brunswick Units 1 and 2 Power I Flow Map ................................................................................ 14 Figure 4 Radial Power Distribution Map for Brunswick Unit 1 Cycle 21 SLMCPR [

] .................................................................................................................................. 15 Figure 5 Radial Power Distribution Map for Brunswick Unit 2 Cycle 23 SLMCPR [

] .................................................................................................................................. 16 Figure 6 Channel Fluence Gradient Distribution for Brunswick Unit 1 Cycle 21 ........................................ 17 Figure 7 Channel Fluence Gradient Distribution for Brunswick Unit 2 Cycle 23 ........................................ 18 AREVA- Fuel BL This document is sub*ect to the restrictions set forth on the first or title a e

No FS 1-0028339 Rev. 1.0 Brunswick Unit 1 Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM3D Methodology A

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1. PURPOSE Reference 1 presents an AREVA methodology for determining the safety limit minimum critical power ratio (SLMCPR) that was approved by the NRC. The SLMCPR methodology incorporates full implementation of the ACE critical power correlation (Reference 2), a realistic fuel channel bow model (Reference 4), and expanded coupling with the MICROBURN-B2 core simulator (Reference 5). More detailed descriptions are discussed in Reference 1. The purpose of this report is to provide SLMCPR results for Brunswick Unit 1 Cycle 21 (BRK1-21) and Brunswick Unit 2 Cycle 23 (BRK2-23) operating in the currently licensed MELLLA domain and using the Reference 1 methodology to support a change in the Technical Specification SLMCPR values for two-loop operation (TLO) and single-loop operation (SLO).
2. METHODOLOGY The analysis presented in this document used the methodology presented in Reference 1. The SLMCPR is defined as the minimum value of the critical power ratio which ensures that at least 99.9% of the fuel rods in the core are expected to avoid boiling transition during normal operation or an anticipated operational occurrence (AOO). The SLMCPR is determined using a statistical analysis that employs a Monte Carlo process that perturbs key input parameters used in the calculation of MCPR. The set of uncertainties used in the statistical analysis include both fuel-related and plant-related uncertainties.

The SLMCPR analysis is performed with a power distribution that conservatively represents expected reactor operating states that could both exist at the operating limit MCPR (OLMCPR) and produce a MCPR equal to the SLMCPR during an AOO. [

]

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No FS 1-0028339 Rev. 1.0 Brunswick Unit 1 Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM3D Methodology A

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[

]

In the AREVA methodology, the effects of channel bow on the critical power performance are accounted for in the SLMCPR analysis. Reference 1 discusses the application of a realistic channel bow model.

3. ANALYSIS The core loading and cycle depletion from the Brunswick Unit 1 Cycle 21 (BRK1-21 ) and Brunswick Unit 2 Cycle 23 (BRK2-23) fuel cycle designs were used as the bases of the SLMCPR analyses. Figure 1 and Figure 2 present the core loading including the assembly type, the cycle the fuel was originally loaded,
  • and the number of assemblies for BRK1-21 and BRK2-23 respectively. The BRK1-21 core is made up of ATRIUM' 10XM* fuel and the BRK2-23 core is made up of ATRIUM 10XM fuel and eight ATRIUM 11 lead test assemblies (LTAs). Analyses were performed [

] for the Brunswick power/flow map for MELLLA operation as shown in Figure 3. The BSP regions shown in the power/flow map are based on the methods discussed in Reference 3. The radial power distribution [

] is presented in Figure 4 and Figure 5.

The calculated fast fluence gradients for the BRK1-21 and BRK2-23 core designs have been compared to the upper and lower bounds of the channel bow database. As shown in Figure 6 and Figure 7, the BRK1-21 and BRK2-23 reference core designs remain bounded by the upper/lower bound of the channel bow database [ ] . The channel bow model uncertainty for the assemblies that experience fluence gradients outside the bounds of the measurement database was augmented with the process discussed in the Reference 9 licensing condition.

The ACE/ATRIUM 1OXM critical power correlation (Reference 2) is used for the ATRIUM 1OXM fuel while the SPCB critical power correlation (Reference 7) is used for the ATRIUM 11. The fuel- and plant-related uncertainties used in the BRK1-21 and BRK2-23 SLMCPR analyses are presented in Table 1. The radial

  • ATRIUM is a trademark of AREVA Inc.

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No FS 1-0028339 Rev. 1.0 Brunswick Unit 1 Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM3D Methodology A

Handling: Restricted AREVA Page 7/18 AREVA (Non-Proprietary Version} I and nodal power uncertainties used in the analysis include the effects of up to 40% of the TIP channels out-of-service, up to 50% of the LPRMs out-of-service, and a 2500 effective full power hour (EFPH) LPRM calibration interval.

The SPCB (Reference 7) and ACE/ATRIUM 10XM (Reference 2) critical power correlation limit of applicability for local peaking factor is [ ], provided as an SER restriction when the correlations were approved by the NRC. Fuel expected to be resident in BRK1-21 and BRK2-23 has been designed to be below this limit. The maximum local peaking factor for the fresh ATRIUM 1OXM lattice is [ ] . During each Monte Carlo trial of the SLMCPR calculation, [

]. The base additive constant uncertainty and the high pin power additive constant uncertainty values are presented in Table 3-2 of the SAFLIM3D topical report (Reference 1).

The BRK1-21 and BRK2-23 SLMCPR analyses support a TLO SLMCPR of 1.05 and an SLO SLMCPR of 1.07. Table 2 and Table 3 present summaries of results including the SLMCPR and the percentage of rods expected to experience boiling transition. The percentages of the total number of fuel rods predicted to experience boiling transition in the overall Monte Carlo statistical evaluation associated with each nuclear fuel type are presented in Table 4 and Table 5. The results are for the [

].

4. DISCUSSION OF RESULTS Results of the SLMCPR analyses using the Reference 1 methodology based on the BRK1-21 and BRK2-23 design step-through and the Table 1 fuel- and plant-related uncertainties are shown in Table 4 (BRK1-21) and Table 5 (BRK2-23). The results show that a reduction in the Technical Specification for TLO and SLO SLMCPR can be supported.

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5. REFERENCES
1. ANP-10307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011.
2. ANP-10298PA Revision 1, ACE/ATRIUM 10XM Critical Power Correlation, AREVA NP, March 2014.
3. OG02-0119-260, Backup Stability Protection (BSP) for Inoperable Option Ill Solution, GE Nuclear Energy, July 17, 2002.
4. BAW-10247PA Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP, February 2008.
5. EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors:

Evaluation and Validation of CASM0-4 I MICROBURN-B2, Siemens Power Corporation, October 1999.

6. EMF-2493(P) Revision 0, MICROBURN-82 Based Impact of Failed/Bypassed LPRMs and TIPs, Extended LPRM Calibration Interval, and Single Loop Operation on Measured Radial Bundle Power Uncertainty, Siemens Power Corporation, December 2000.
7. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.
8. Letter, H. Donald Curet (AREVA) to H.J. Richings (USNRC), "POWERPLEX Core Monitoring:

Failed or Bypassed Instrumentation and Extended Calibration," HDC:96:012, May 6, 1996.

(38-9043714-000).

9. Letter, U.S. Nuclear Regulatory Commission to CP&L, "Brunswick Steam Electric Plant, Units 1 and 2 - Issuance of Amendments Regarding Addition of Analytical Methodology Topical Reports to Technical Specification 5.6.5 and Revision to Minimum Critical Power Ratio Safety Limit (TAC NOS. ME8135 and ME8136)," ML13037A551, March 1, 2013.
10. OB21-1305 Revision 1, "Core Monitoring LPRM Uncertainty and Sensitivity Decay," Progress Energy, March 2009 (NRC Accession Number ML092370285).
11. NED0-10958-A, General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application, General Electric, January 1977.
12. NED0-20340, Process Computer Performance Evaluation Accuracy, General Electric, June 1974.
13. NED0-24344, Brunswick Steam Electric Plant Units 1 and 2 Single-Loop Operation, General Electric, September 1981.

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Table 1 Fuel- and PlantmRelated Uncertainties for Brunswick SLMCPR Analyses Parameter Uncertainty Reference Fuel-Related Uncertainties

[

]

Plant-Related Uncertainties Feedwater flow rate 1.8%+ 11 Feedwater temperature 0.8%+ 11 Core pressure 0.8%+.§ 12 Total core flow rate TLO 2.5% 11 SLO 6.0% 13

  • [ ]

t [

]

j:

Referenced plant uncertainties were rounded up to the nearest 0.1 % before use.

§ The core pressure uncertainty is taken in Reference 12 to be a more conservative value than accepted in Reference 11; therefore, the more conservative value is used.

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Table 2 Results Summary for Brunswick Unit 1 Cycle 21 SLMCPR Analysis Percentage of Rods in Boiling SLMCPR Transition TL0-1.05 0.0667 SL0-1.07 0.0942 Table 3 Results Summary for Brunswick Unit 2 Cycle 23 SLMCPR Analysis Percentage of Rods in Boiling SLMCPR Transition TL0-1.05 0.0919 SL0-1.07 0.0782 AREVA- Fuel BL This document is sub'ect to the restrictions set forth on the first or title a e

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Table 4 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type for Brunswick Unit 1 Cycle 21 Contribution of Total Rods Nuclear Predicted to be in BT(%)

Fuel Fuel Burnup Type Design Status TLO SLO 34 ATRIUM 10XM Twice burned [

35 ATRIUM 10XM Twice burned 36 ATRIUM 10XM Once burned 37 ATRIUM 10XM Once burned 38 ATRIUM 10XM Fresh 39 ATRIUM 10XM Fresh 40 ATRIUM 10XM Fresh 1

Table 5 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type for Brunswick Unit 2 Cycle 23 Contribution of Total Rods Nuclear Predicted to be in BT(%)

Fuel Fuel Burn up Type Design Status TLO SLO 34 ATRIUM 10XM Twice burned [

35 ATRIUM 10XM Twice burned 36 ATRIUM 10XM Twice burned 37 ATRIUM 10XM Twice burned 38 ATRIUM 10XM Once burned 39 ATRIUM 10XM Once burned 40 ATRIUM 11 Once burned 41 ATRIUM 10XM Fresh 42 ATRIUM 10XM Fresh 43 ATRIUM 10XM Fresh 1

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No FS 1-0028339 Rev. 1.0 Brunswick Unit 1 Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM3D Methodology A

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~

60.0 0

a.

~ 50.0 40.0 30.0 20.0 10.0 0.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hrCore Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow Figure 3 Brunswick Units 1 and 2 Power I Flow Map AREVA- Fuel BL This document is sub ect to the restrictions set forth on the first or title a e

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J: 1 2 3 4 5 6 7 8 9 10 11 12 13 I:

1 0.278 0.347 0.396 0.413 0.415 2 0.362 0.495 0.675 0.741 0.767 0.771 3 0.270 0.374 0.469 0.582 0.782 1.004 1.087 1.119 0.974 4 0.311 0.491 0.701 0.804 0.965 1.035 1.112 1.206 1.092 1.283 5 0.268 0.487 0.777 1.018 1.108 0.991 0.825 0.962 1.264 1.337 1.172 6 0.369 0.693 1.017 1.176 1.125 1.219 0.989 0.879 1.316 1.191 1.395 7 0.463 0.798 1.104 1.109 1.328 1.325 1.149 1.330 1.196 1.397 1.203 8 0.367 0.589 0.965 0.976 1.212 1.321 1.175 1.403 1.214 1.409 1.199 1.332 9 0.281 0.504 0.782 1.036 0.810 0.972 1.122 1.397 1. 233 1. 439 1.225 1.341 0.875 10 0.356 0.681 1.012 1.117 0.952 0.866 1.325 1.207 1.441 1. 243 1.421 1.160 1.009 11 0.395 0.760 1.095 1.216 1.275 1.324 1.197 1.414 1.224 1.424 1.209 1.397 1.156 12 0.414 0.759 1.126 1.101 1.353 1.193 1.409 1.206 1. 350 1.158 1.398 1.212 1.440 13 0.415 0.763 0.962 1.295 1.193 1.413 1.221 1.345 0.880 1.014 1.151 1.441 1.221 14 0.415 0.771 0.965 1.297 1.194 1.415 1.213 1.345 0.880 1.014 1.152 1.441 1.439 15 0.412 0.768 1.132 1.106 1.360 1.203 1.412 1.205 1. 349 1.155 1.397 1.210 1.442 16 0.400 0.755 1.106 1.228 1.287 1.334 1.200 1.416 1.221 1.423 1.201 1.397 1.158 17 0.361 0.697 1.033 1.136 0.977 0.884 1.332 1.207 1.441 1.240 1.422 1.160 1.013 18 0.296 0.586 0.811 1.059 0.833 0.995 1.127 1.399 1. 231 1. 439 1.225 1.343 0.877 19 0.379 0.605 0.984 0.997 1.224 1.327 1.173 1.402 1.213 1.410 1.200 1.336 20 0.479 0.809 1.116 1.117 1.333 1.327 1.135 1. 331 1.197 1.400 1.205 21 0.369 0.703 1.024 1.182 1.125 1.223 0.993 0.893 1.319 1.192 1.397 22 0.268 0.489 0.779 1.021 1.112 1.005 0.829 0.966 1.267 1.339 1.182 23 0.302 0.488 0.701 0.807 0.972 1.042 1.116 1.207 1.085 1.281 24 0.269 0.375 0.473 0.587 0.785 1.007 1.087 1.117 0.967 25 0.363 0.498 0.677 0.745 0.762 0.760 26 0.278 0.344 0.392 0.408 0.417 J:l4 15 16 17 18 19 20 21 22 23 24 25 26 I:

1 0.414 0.409 0.393 0.344 0.279 2 0.761 0.766 0.742 0.676 0.499 0.365 3 0.970 1.118 1.086 1.005 0.784 0.603 0.477 0.375 0.268 4 1. 282 1. 091 1.205 1.112 1.038 0.970 0.806 0.698 0.483 0.300 5 1.182 1. 336 1.261 0.960 0.825 1.000 1.108 1.015 0.773 0.483 0.267 6 1.394 1.188 1.312 0.875 0.986 1.216 1.119 1.174 1.015 0.696 0. 371 7 1.202 1.393 1.190 1.321 1.127 1.319 1.325 1.108 1.106 0.793 0.475 8 1.331 1.195 1.402 1.205 1.393 1.168 1.319 1.215 0.990 0.970 0.592 0.364 9 0.874 1.336 1.218 1.430 1.223 1.391 1.120 0.988 0.825 1.043 0.785 0.499 0.279 10 1.008 1.154 1.414 1.233 1.433 1.200 1.324 0.877 0.968 1.122 1. 012 0.677 0.349 11 1.146 1.391 1.194 1.417 1.213 1.409 1.192 1.325 1.276 1.217 1.095 0.745 0.390 12 1.439 1.205 1.392 1.151 1.345 1.200 1.406 1.189 1.352 1. 091 1.130 0.781 0.414 13 1.437 1.440 1.150 1.013 0.878 1.343 1.217 1.410 1.189 1. 296 0.979 0.784 0.422 14 1.226 1.441 1.151 1.015 0.892 1.345 1.218 1.411 1.190 1.297 0.966 0.784 0.426 15 1.442 1.211 1.399 1.158 1.351 1.204 1.409 1.190 1.356 1.104 1.133 0.784 0.418 16 1.150 1.398 1.207 1.425 1.222 1.414 1.196 1.329 1.282 1. 224 1.103 0.744 0.399 17 1.012 1.162 1.421 1.241 1.440 1.205 1.328 0.879 0.972 1.130 1. 027 0.692 0.354 18 0.878 1.342 1.224 1.436 1.229 1.395 1.122 0.989 0.827 1.051 0.797 0.586 0 .296 19 1.335 1.200 1.405 1.208 1.395 1.169 1.320 1.215 0.982 0.976 0.604 0.378 20 1.204 1.394 1.190 1.317 1.127 1.316 1.323 1.106 1.106 0.802 0.478 21 1.394 1.186 1.305 0.855 0.961 1.206 1.113 1.172 1.016 0.693 0.376 22 1.165 1.331 1.252 0.935 0.800 0.976 1.099 1.012 0.772 0.486 0.269 23 1.279 1.087 1.197 1.100 1.024 0.957 0.798 0.695 0.485 0.310 24 0.969 1.113 1.079 0.997 0.774 0.587 0.468 0.376 0.269 25 0.765 0.761 0.736 0.669 0.494 0.364 26 0.412 0.406 0.392 0.344 0.276 Figure 4 Radial Power Distribution Map for Brunswick Unit 1 Cycle 21 SLMCPR

[ ]

AREVA- Fuel BL This document is sub"ect to the restrictions set forth on the first or title a e

No FS 1-0028339 Rev. 1.0 Brunswick Unit 1 Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM3D Methodology A

Handling: Restricted AREVA Page 16/18 AREVA (Non-Proprietary Version)

J: 1 2 3 4 5 6 7 8 9 10 11 12 13 I:

1 0.252 0.313 0.367 0.384 0.382 2 0.341 0.484 0.668 0.741 0.741 0.721 3 0.187 0.285 0.396 0.562 0.818 1.088 1.150 1.163 0.954 4 0.207 0.356 0.488 0.705 0.864 1.188 1.285 1.102 1.330 1.317 5 0.176 0.353 0.612 0.777 0.910 1.208 1.320 1.372 1.408 1. 405 1.150 6 0.270 0.484 0.774 1.105 1.230 1.103 1.364 1.153 1. 429 1.163 1. 403 7 0.400 0.697 0.903 1.222 1.308 1.353 1. 153 1. 419 1.154 1.407 1.127 8 0.337 0.550 0.852 1.191 1.082 1.338 1.144 1.407 1.162 1.408 1.137 1.375 9 0.254 0.481 0. 813 1.171 1.297 1.335 1.124 1.375 1.169 1.419 1.157 1.385 1.135 10 0.327 0.660 1.079 1. 269 1.348 1.129 1.370 1.134 1.407 1.160 1. 388 1.145 1.377 11 0.368 0.739 1.144 1.100 1.386 1.399 1.139 1.382 1.134 1.385 1.142 1.372 1.124 12 0.388 0.743 1.162 1. 322 1.387 1.142 1.379 1.117 1.371 1.125 1. 364 1.122 1. 352 13 0.387 0.728 0.970 1. 319 1.135 1.375 1.105 1.349 1.112 1.353 1.103 1.338 1. 071 14 0.386 0.741 0.961 1. 317 1.133 1.371 1.099 1.340 1.100 1.333 1. 084 1. 314 1.068 15 0.388 0.739 1.156 1. 315 1.378 1.132 1.361 1.095 1.325 1.072 1.278 1.056 1. 294 16 0.372 0. 720 1.136 1.081 1.374 1.382 1.110 1.338 1. 075 1. 269 1. 010 1. 210 1. 039 17 0.327 0.654 1.070 1. 258 1.334 1.113 1.338 1.090 1.314 1.027 0.981 0.822 1.225 18 0.250 0.477 0.804 1.161 1.283 1.315 1.097 1.321 1.085 1.255 0.827 0.982 1.012 19 0.332 0.551 0.845 1.177 1.068 1.307 1.093 1.331 1.068 1.248 1.013 1.265 20 0.394 0.693 0.895 1.204 1.281 1.313 1.105 1.343 1. 082 1.318 1. 070 21 0.285 0.493 0.772 1.094 1.208 1.061 1. 324 1.113 1. 375 1.118 1.359 22 0.193 0.362 0.617 0.776 0.900 1.187 1.293 1.342 1. 375 1. 373 1.127 23 0.214 0.372 0.563 0.704 0.851 1.170 1.265 1. 098 1. 310 1.299 24 0.201 0.294 0.414 0.561 0.806 1.075 1.138 1.150 0.943 25 0.342 0.481 0.661 0.721 0.733 0.729 26 0.252 0.326 0.371 0.384 0.386 J:l4 15 16 17 18 19 20 21 22 23 24 25 26 I:

1 0.384 0.388 0.376 0.330 0.259 2 0.719 0.740 0.741 0.668 0.486 0.344 3 0.951 1.163 1.150 1.089 0.817 0.564 0.407 0.284 0.190 4 1.316 1.330 1.100 1.285 1.188 0.862 0.702 0.489 0.362 0.224 5 1.150 1.404 1.408 1.372 1.320 1.208 0.910 0.778 0.621 0.372 0.197 6 1.403 1.161 1.428 1.150 1.363 1.101 1.230 1.108 0.784 0.573 0.306 7 1.127 1.406 1.151 1.419 1.151 1.353 1.309 1.225 0.909 0.708 0. 415 8 1.375 1.136 1.408 1.162 1.409 1.131 1.340 1.085 1.196 0.858 0.561 0.344 9 1.134 1.385 1.156 1.419 1.165 1.376 1.119 1.339 1.303 1.178 0.815 0.485 0.258 10 1.376 1.144 1. 386 1.159 1.409 1.131 1.375 1.133 1.356 1.275 1. 084 0.663 0.335 11 1.122 1.362 1.135 1.386 1.138 1.392 1.146 1.411 1.397 1.097 1.149 0.743 0.373 12 1.352 1.119 1. 362 1.133 1.384 1.133 1.398 1.157 1.401 1.333 1.169 0.746 0.388 13 1.074 1.351 1.120 1.377 1.135 1.377 1.137 1.402 1.154 1.334 0. 968 0.730 0.385 14 1.067 1.347 1.119 1.378 1.136 1.378 1.138 1.403 1.150 1.334 0. 968 0. 729 0.388 15 1.319 1.113 1. 366 1.135 1.388 1.135 1.401 1.159 1.403 1.334 1.169 0.746 0.389 16 1.075 1.342 1.134 1.387 1.141 1.396 1.151 1.415 1.400 1.098 1.150 0.742 0.378 17 1.297 1.113 1.370 1.155 1.411 1.141 1.383 1.138 1.360 1.278 1. 085 0.663 0.329 18 1.069 1.342 1.137 1.411 1.171 1.383 1.130 1.346 1.308 1.180 0.815 0.482 0.254 19 1.308 1.106 1.387 1.153 1.407 1.156 1.347 1.095 1.199 0.856 0.554 0.341 20 1.087 1.376 1.139 1.410 1.148 1.356 1.314 1.229 0.907 0.700 0.406 21 1.370 1.143 1.415 1.145 1.362 1.103 1.233 1.109 0.777 0.495 0.282 22 1.132 1.389 1.397 1.367 1.318 1.209 0.912 0.779 0.616 0.359 0.180 23 1.302 1.319 1.093 1.281 1.186 0.861 0.705 0.498 0.363 0.218 24 0.944 1.155 1.144 1.084 0.815 0.562 0.415 0.278 0.187 25 0.716 0.736 0.736 0.664 0.485 0.345 26 0.384 0.383 0.368 0.323 0.254 Figure 5 Radial Power Distribution Map for Brunswick Unit 2 Cycle 23 SLMCPR

[ ]

AREVA- Fuel BL This document is sub*ect to the restrictions set forth on the first or title a e

No FS 1-0028339 Rev. 1.0 Brunswick Unit 1 Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM3D Methodology A

Handling: Restricted AREVA Page 17/18 AREVA (Non-Proprietary Version)

Figure 6 Channel Fluence Gradient Distribution for Brunswick Unit 1 Cycle 21 AREVA- Fuel BL This document is sub*ect to the restrictions set forth on the first or title a e

No FS 1-0028339 Rev. 1.0 Brunswick Unit 1 Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM3D Methodology A

Handling: Restricted AREVA Page 18/18 AREVA (Non-Proprietary Version)

Figure 7 Channel Fluence Gradient Distribution for Brunswick Unit 2 Cycle 23 AREVA- Fuel BL This document is sub'ect to the restrictions set forth on the first or title a e

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