ML13070A323

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51-9191259-001, Brown Ferry Units Cycle 19 MCPR Safety Limit Analysis with SAFLIM3D Methodology
ML13070A323
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/30/2012
From: Tylinski S
AREVA NP
To:
Office of Nuclear Reactor Regulation
References
51-9191259-001
Download: ML13070A323 (17)
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Text

ATTACHMENT 26 Browns Ferry Nuclear Plant (BFN)

Units 1, 2, and 3 Technical Specifications (TS) Change 478 Addition of Analytical Methodologies to Technical Specification 5.6.5.b for Browns Ferry 1, 2, & 3, and Revision of Technical Specification 2.1.1.2 for Browns Ferry Unit 2, in Support of ATRIUM-10 XM Fuel Use at Browns Ferry Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis with SAFLIM3D Methodology (Non-Proprietary)

Attached is the non proprietary version of the SLMCPR report for Unit 2 cycle 19.

This report supports the change to Technical Specification 2.1.1.2 for Unit 2.

A 20004-018 (10/18/2010)

AREVA AREVA NP Inc.

Engineering Information Record Document No.: 51 - 9191259 - 001 Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology Page 1 of 16

A 20004-018 (10/18/2010)

Document No.: 51-9191259-001 AR EVA Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology Safety related? YES i- NO D)oes this document contain assumptions requiring verification? I YES NO Does this document contain Customer Required Format? i YES [ NO Signature Block P/LP, R/LR, Pages/Sections Name and AIA-CRF, Prepared/Reviewed/

Title/Discipline Signature AJA-CRI Date Approved or Comments S.A. Tylinski, Engineer P Thermal-Hydraulics Richland 3/4 1 I. f I/

D. D. Crockett, Engineer R 1°/;

Thermal-Hydraulics Richland /

D.W. Pruitt, Manager AIA-CRI Thermal-Hydraulics Richland A.B. Meginnis, Manager A Product Licensing .%  : _________

1 //2 -/ 4If Note: P/LP designates Preparer (P), Lead Preparer (LP)

R/LR designates Reviewer (R), Lead Reviewer (LR)

A/A-CRF designates Approver (A), Approver of Customer Requested Format (A-CRF)

AIA-CRI designates Approver (A), Approver - Confirming Reviewer Independence (A-CRI)

Record of Revision Revision Pages/Sections!

No. Paragraphs Changed Brief Description I Change Authorization 000 Initial issue.

This is the nonproprietary version of 51-9191258-000.

001 All This document is revised to keep the revision number the same as the proprietary version. No other changes have been made to this document Page 2

A 20004-018 (10/18/2010)

Document No.: 51-9191259-001 AR EVA Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology Table of Contents 1 .0 P UR P OS E ................................................................................................................................. 4 2 .0 MET H O D O LO G Y ....................................................................................................................... 4 3 .0 A NA LY S IS ................................................................................................................................. 5 4.0 DISCUSSION OF RESULTS ................................................................................................. 6 5 .0 R E F E R E NC E S ........................................................................................................................... 6 Tables TABLE 1 FUEL- AND PLANT-RELATED UNCERTAINTIES MCPR SAFETY LIMIT ANALYSES ......... 8 TABLE 2 RESULTS

SUMMARY

FOR MCPR SAFETY LIMIT ANALYSIS ......................................... 9 TABLE 3 CONTRIBUTION OF TOTAL PREDICTED RODS IN BT BY NUCLEAR FUEL TYPE ..... 9 Figures FIGURE 1 BROWNS FERRY UNIT 2 CYCLE 19 CORE LOADING MAP .................................. 10 FIGURE 2 BROW NS FERRY POW ER / FLOW MAP ................................................................ 11 FIGURE 3 RADIAL POWER DISTRIBUTION MAP FOR BROWNS FERRY UNIT 2 CYCLE 19 SLMCPR [ I ................................................ 12 FIGURE 4 RADIAL POWER DISTRIBUTION FOR TLO LIMITING EXPOSURE OF

[ I ............................................................................................. . . 13

[

.............................................. 14

[

]............................................... 15 C

].............................................. 16 Page 3

A AR EVA Document No.: 51-9191259-001 Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology 1.0 PURPOSE Reference 1 presents an AREVA methodology for determining the safety limit minimum critical power ratio (SLMCPR) that was recently approved by the NRC. The methodology is an update or extension of the previously approved methodology presented in Reference 2. The SLMCPR methodology was updated to incorporate full implementation of the ACE critical power correlation (References 3, 4, and 5), a realistic fuel channel bow model (Reference 6), and expanded coupling with the MICROBURN-B2 core simulator (Reference 7). More detailed descriptions of these improvements are discussed in Reference 1. The purpose of this report is to provide SLMCPR results for Browns Ferry Unit 2 Cycle 19 using the Reference 1 methodology to support a change in the list of approved methodologies in the Technical Specifications and also a change in the Technical Specification SLMCPR values for two-loop operation (TLO) and single-loop operation (SLO).

2.0 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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A AR EVA Document No.: 51-9191259-001 Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology 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.

3.0 ANALYSIS The final core design and step-through, developed by AREVA NP to meet the operating requirements specified by TVA, was used in the BFE2-19 MCPR safety limit analysis. The BFE2-19 design supports licensed rated power of 3,458 MWt and operation to licensing end of cycle (EOC) cycle exposure of approximately 16,941 MWd/MTU. The design includes extensions for final feedwater temperature reduction (FFTR) and coastdown. Figure 1 presents the core loading, the cycle the fuel was originally loaded, and the number of assemblies. The BFE2-19 core is made up of ATRIUM TM 1OXM* and ATRIUM-10 fuel. Analyses were performed [

] for the Browns Ferry power/flow map for MELLLA operation as shown in Figure 2. The radial power distribution [ ] is presented in Figures 3 and 4.

The ACE/ATRIUM 1OXM critical power correlation (References 3, 4, and 5) is used for the ATRIUM 10XM fuel while the SPCB critical power correlation (Reference 8) is used for the ATRIUM-10. The fuel- and plant-related uncertainties used in the BFE2-19 SLMCPR analysis are presented in Table 1.

The radial 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 BFE2-19 SLMCPR analysis supports a TLO SLMCPR of 1.04 and an SLO SLMCPR of 1.05.

Table 2 presents a summary of the analysis results including the SLMCPR and the percentage of rods

  • ATRIUM is a trademark of AREVA NP.

Page 5

A Document No.: 51-9191259-001 AR EVA Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology 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 3. The results are for the [

1. The BFE2-19 fuel design is presented in Figures 5 through 7.

4.0 DISCUSSION OF RESULTS Compared to the current TLO and SLO SLMCPR limits using the Reference 2 methodology, results show a significant decrease in both the TLO and SLO SLMCPR limits with the Reference 1 methodology. The SLMCPR differences are primarily a result of the following differences in the methodologies:

  • Implementation of the realistic channel bow model
  • Explicit use of the [ ] as a result of the expanded coupling with MICROBURN-B2 The improved SLMCPR results with the Reference 1 methodology are consistent with the results presented in Tables 4-1 and 4-3 of Reference 1.

5.0 REFERENCES

1. ANP-10307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011.
2. ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF CriticalPower Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.
3. ANP-10298PA Revision 0, ACE/ATRIUM 1OXM CriticalPower Correlation,AREVA NP, March 2010.
4. ANP-3140(P) Revision 0, "Browns Ferry Units 1, 2, and 3 Improved K-factor Model for ACE/ATRIUM 1OXM Critical Power Correlation," AREVA NP, August 2012.
5. ANP-10298PA Revision 0 Supplement 1P Revision 0, Improved K-factor Model for ACE/ATRIUM 1OXM Critical Power Correlation, AREVA NP, December 2011.
6. BAW-1 0247PA Revision 0, Realistic Thermal-MechanicalFuel Rod Methodology for Boiling Water Reactors, AREVA NP, February 2008.

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A Document No.: 51-9191259-001 AR EVA Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology

7. EMF-2158(P)(A) Revision 0, Siemens Power CorporationMethodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4 / MICROBURN-B2, Siemens Power Corporation, October 1999.
8. EMF-2209(P)(A) Revision 3, SPCB CriticalPower Correlation,AREVA NP, September 2009.
9. 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).

Page 7

A Document No.: 51-9191259-001 AREVA Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology Table 1 Fuel- and Plant-Related Uncertainties MCPR Safety Limit Analyses Standard Parameter Deviation Fuel-Related Uncertainties Plant-Related Uncertainties Feedwater flow rate 1.8%

Feedwater temperature 0.8%

Core pressure 0.7%

Total core flow rate TLO 2.5%

SLO 6.0%

  • [

I Page 8

A Document No.: 51-9191259-001 AREVA Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology Table 2 Results Summary for MCPR Safety Limit Analysis Percentage of Rods in Boiling SLMCPR Transition TLO - 1.04 0.0834 SLO - 1.05 0.0921 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type Contribution of Total Rods Nuclear Predicted to be in BT (%)

Fuel Fuel Burnup TLO SLO Type Design Status [ ] [ ]

10 ATRIUM-10 Twice burned [

11 ATRIUM-10 Twice burned 12 ATRIUM-10 Once burned 13 ATRIUM-10 Once burned 14 ATRIUM-10 Once burned 15 ATRIUM 1OXM Fresh 16 ATRIUM 1OXM Fresh 17 ATRIUM 1OXM Fresh ]

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A Document No.: 51-9191259-001 AREVA Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology 10 11 11 10 11 10 11 11 10 11 10 11 11 10 11 11 13 14 13 14 14 13 14 10 13 10 11 11 11 11 10 14 14 12 14 14 11 11 14 14 11 12 14 14 10 11 11 15 15 15 15 15 13 10 13 12 15 15 11 15 12 12 15 15 15 15 12 10 10 10 14 14 16 13 16 17 12 17 17 12 17 11 16 13 16 14 14 10 10 11 10 10 13 15 17 13 17 11 16 13 16 12 12 16 13 16 11 17 13 17 15 13 10 10 13 14 15 15 10 17 12 17 14 17 12 17 17 12 17 14 17 12 17 10 15 15 14 13 10 10 12 14 17 10 17 13 16 12 17 12 17 12 12 17 12 17 12 16 13 17 10 17 14 12 10 13 10 14 15 16 13 17 13 17 12 17 12 17 12 17 17 12 17 12 17 12 17 13 17 13 16 15 14 11 10 11 14 15 13 17 12 16 12 17 12 17 12 13 12 12 13 12 17 12 17 12 16 12 17 13 15 14 14 11 11 13 11 15 16 11 17 12 17 12 17 12 17 12 17 17 12 17 12 17 .12 17 12 17 11 16 15 12 13 11 10 10 11 15 11 16 14 17 12 17 12 17 12 17 12 12 17 12 17 12 17 12 17 14 16 11 15 11 14 10 11 14 14 15 17 13 17 12 17 12 17 12 17 12 17 17 12 17 12 17 12 17 12 17 13 17 15 14 14 11 10 13 14 15 12 16 12 17 12 13 12 17 12 17 12 12 17 12 17 12 13 12 17 12 16 12 15 14 13 10 i-i 14 12 12 17 12 12 12 12 17 12 11 11 17 17 12 17 12 17 10 10 17 12 17 12 17 12 17 11 14 11 14 11 12 17 12 17 12 17 12 17 12 17 12 10 10 12 17 12 17 12 17 12 17 12 17 12 11 14 11 10 13 14 15 12 16 12 17 12 13 12 17 12 17 12 12 17 12 17 12 13 12 17 12 16 12 15 14 13 10 11 14 15 13 17 17 12 12 12 17 14 14 17 12 17 12 17 17 17 17 12 12 17 12 17 13 17 15 14 11 10 11 11 15 11 16 14 17 12 17 12 17 12 17 12 12 17 12 17 12 17 12 17 14 16 11 15 11 10 10 11 13 12 15 16 11 17 12 17 12 17 12 17 12 17 17 12 17 12 17 12 17 12 17 11 16 15 12 13 11 11 11 15 17 12 17 13 14 13 12 16 12 17 12 12 12 13 12 17 12 17 12 16 12 17 13 15 14 11 10 11 15 13 17 12 12 12 17 17 14 16 17 13 17 12 17 17 17 17 12 12 17 13 13 16 15 14 11 10 10 10 12 14 17 10 17 13 16 12 17 12 17 12 12 17 12 17 12 16 13 17 10 17 14 12 10 11 11 13 14 15 15 10 17 12 17 14 17 12 17 17 12 17 14 17 12 17 10 15 15 14 13 11 11 10 10 13 15 17 13 17 11 16 13 16 12 12 16 13 16 11 17 13 17 15 13 10 10 11 10 10 14 14 16 13 16 11 17 12 17 17 12 17 11 16 13 16 14 14 10 10 10 13 12 15 15 15 15 15 15 12 12 15 15 15 15 15 15 12 13 10 11 11 10 14 14 12 11 14 14 11 11 14 14 11 12 14 14 10 11 11 10 11 10 13 10 14 13 14 14 13 14 11 13 11 11 II 10 11 11 10 11 10 11 11 10 11 10 11 11 10

.Nuclear Fuel Cycle Number of Fuel Type Description Loaded Assemblies 10 ATRIUM-10 17 74 11 ATRIUM-10 17 103 12 ATRIUM-10 18 175 13 ATRIUM-10 18 68 14 ATRIUM-10 18 72 15 ATRIUM 1OXM 19 60 16 ATRIUM 1OXM 19 40 17 ATRIUM 1OXM 19 172 Figure 1 Browns Ferry Unit 2 Cycle 19 Core Loading Map Page 10

A Document No.: 51-9191259-001 AREVA Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology E

0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow (% of Rated)

Figure 2 Browns Ferry Power / Flow Map Page 11

A Document No.: 51-9191259-001 ARE VA Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology 0.194 0.250 0.284 0.291 0.313 0.308 0.312 0.278 0.388 0.521 0.614 0.577 0.666 0.659 0.664 0.201 0.335 0.478 0.749 0.856 0.852 0.754 0.898 0.906 0.763 0.330 0.620 0.819 1.075 1.169 1.202 1.222 1.238 1.233 1.048 0,337 0.515 0.855 0.998 1.215 1.113 1.302 1.036 1.335 1.169 1.340 0.201 0.328 0.515 0.827 1.131 1.235 1.137 1.340 1.066 1.371 1.189 1.392 1.221 0.326 0.617 0.854 1.130 1.253 1.042 1.361 1.201 1.404 1.222 1.390 1.201 1.388 0.270 0.464 0.812 0.994 1.231 1.041 1.360 1.210 1.429 1.234 1.388 1.151 1.310 1.158 0.184 0.370 0.735 1.063 1.207 1.133 1.356 1.208 1.429 1.255 1.438 1.186 1.003 0.859 1.257 0.233 0.431 0.838 1.154 1.106 1.332 1.196 1.421 1.249 1.447 1.259 1.358 0.880 0.846 1.089 0.268 0.589 0.827 1.187 1.290. 1.061 1.394 1.224 1.421 1.238 1.431 1.211 1.335 1.134 1.343 0.278 0.539 0.741 1.207 1.028 1.360 1.215 1.376 1.162 1.346 1.215 1.426 1.226 1.416 1.232 0.307 0.656 0.889 1.225 1.320 1.181 1.380 1.154 1.000 0.879 1.342 1.240 1.448 1.251 1.440 0.306 0.653 0.897 1.219 1.155 1.375 1.201 1.303 0.858 0.847 1.147 1.422 1.250 1.420 1.217 0.311 0.659 0.757 1.035 1,312 1.189 1.371 1.148 1.250 1.078 1.342 1.232 1.426 1.198 1.018 0.311 0.659 0.758 1.035 1.312 1.189 1.370 1.147 1.248 1.077 1.341 1.231 1.426 1.197 1.017 0.308 0.656 0.900 1.221 1.156 1.375 1.200 1.300 0.854 0.843 1.145 1.420 1.250 1.419 1.218 0.312 0.663 0.894 1.230 1,323 1.182 1.379 1.151 0.995 0.874 1.338 1.239 1.447 1.252 1.440 0.288 0.575 0.751 1.216 1,031 1.361 1.214 1.374 1.160 1.342 1.214 1.424 1.227 1.415 1.236 0.284 0.613 0.851 1.197 1.294 1.061 1.392 1.221 1.417 1.236 1.428 1.217 1.335 1.136 1.344 0.252 0.520 0.854 1.164 1.108 1.333 1.194 1.418 1.246 1.444 1.257 1.357 0.883 0.850 1.093 0.196 0.386 0.746 1.070 1.209 1.133 1.354 1.205 1.426 1.252 1.434 1.186 1.005 0.863 1.258 0.268 0.469 0.815 0.994 1.230 1.039 1.356 1.207 1.424 1.231 1.385 1.152 1.310 1.158 0.328 0.617 0.852 1.127 1.24 9 1.041 1.356 1.197 1.399 1.220 1.387 1.201 1.386 0.201 0.328 0.514 0.825 1.127 1.229 1.133 1.333 1.063 1.365 1.186 1.388 1.220 0.336 0.513 0.853 0.993 1.206 1.106 1.2 92 1.030 1.329 1.166 1.338 0.328 0.617 0.813 1.063 1.155 1.188 1.211 1.231 1.229 1.047 0.200 0.331 0.471 0.735 0.839 0.836 0.743 0.892 0.903 0.764 0.263 0.369 0.433 0.591 0.543 0.659 0.656 0.663 0.180 0.231 0.268 0.282 0.307 0.307 0.312 0.311 0.306 0.307 0.281 0.268 0.231 0.181 0.663 0.656 0.658 0.542 0.591 0.432 0.369 0.270 0.763 0.902 0.892 0.743 0.836 0.838 0.735 0.471 0.332 0.200 1.048 1.230 1.2 31 1.211 1.188 1.155 1.062 0.812 0.616 0.328 1.339 1.166 1.330 1.032 1.293 1.106 1.206 0.993 0.852 0.513 0.336 1.221 1.390 1.186 1.365 1.063 1.334 1.132 1.229 1.126 0.824 0.514 0.328 0.201 1.388 1.201 1.388 1.220 1.399 1.196 1.355 1.040 1.248 1.126 0.851 0.616 0.327 1.158 1.311 1.152 1.385 1.230 1.423 1.206 1.355 1.038 1.228 0.993 0.813 0.469 0.276 1.258 0.862 1.004 1.185 1.434 1.251 1.424 1.204 1.352 1.131 1.207 1.068 0.745 0.386 0.196 1.090 0.849 0.882 1.357 1.256 1.443 1.244 1.416 1.192 1.330 1.106 1.162 0.852 0.519 0.252 1.343 1.134 1.334 1.216 1.427 1.234 1.416 1.219 1.389 1.059 1.291 1.194 0.849 0.611 0.283 1.232 1.415 1.225 1.423 1.212 1.341 1.158 1.371 1.211 1.357 1.029 1.212 0.749 0.574 0.287 1.440 1.251 1.446 1.237 1.337 0.873 0.993 1.148 1.376 1.179 1.319 1.226 0.892 0.661 0.311 1.218 1.419 1.248 1.419 1.143 0.842 0.852 1.297 1.197 1.371 1.153 1.218 0.897 0.654 0.307 1.017 1.197 1.424 1.230 1.339 1.075 1.245 1.145 1.367 1.186 1.309 1.033 0.756 0.658 0.311 1.019 1.197 1.424 1.230 1.340 1.076 1.247 1.145 1.367 1.186 1.308 1.032 0.756 0.658 0.310 1.218 1.419 1.249 1.419 1.145 0.846 0.856 1.299 1.198 1.371 1.152 1.216 0.895 0.652 0.306 1.440 1.251 1.445 1.239 1.339 0.877 0.998 1.151 1.376 1.178 1.317 1.222 0.888 0.656 0.306 1.235 1.414 1.225 1.423 1.213 1.343 1.161 1.373 1.212 1.356 1.026 1.205 0.741 0.540 0.278 1.343 1.134 1.332 1.216 1.428 1.236 1.417 1.220 1.390 1.058 1.287 1.185 0.835 0.590 0.268 1.092 0.846 0.879 1.355 1.257 1.444 1.246 1.417 1.193 1.329 1.104 1.152 0.838 0.432 0.234 1.257 0.860 1.001 1.185 1.434 1.252 1.426 1.205 1.353 1.131 1.204 1.061 0.734 0.369 0.184 1.158 1.309 1.151 1.385 1.232 1.425 1.208 1.357 1.040 1.22 9 0.993 0.811 0.464 0.267 1.386 1.201 1.388 1.221 1.401 1.199 1.358 1.043 1.250 1.127 0.853 0.616 0.326 1.221 1.389 1.188 1.368 1.067 1.338 1.136 1.233 1.129 0.826 0.515 0.329 0.201 1.339 1.168 1.333 1.037 1.300 1.112 1.213 0.997 0.856 0.515 0.337 1.048 1.232 1.237 1.220 1.200 1.167 1.074 0.819 0.620 0.330 0.764 0.906 0.898 0.753 0.852 0.857 0.750 0.478 0.334 0.201 0.664 0.660 0.666 0.577 0.614 0.522 0.388 0.276 0.312 0.309 0.313 0.292 0.284 0.251 0.194 Figure 3 Radial Power Distribution Map for Browns Ferry Unit 2 Cycle 19 SLMCPR[ I Page 12

A Document No.: 51-9191259-001 AREVA Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology 200 I I I I I - I - I I I I I I I 175 150 125 4-0 100 L.

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1.15 1.25 1.35 1.45 I El-I Radial Power Peaking Figure 4 Radial Power Distribution for TLO Limiting Exposure of [ I Page 13

A Document No.: 51-9191259-001 AREVA Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology Page 14

A Document No.: 51-9191259-001 AREVA Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology Page 15

A Document No.: 51-9191259-001 AREVA Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology Page 16

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