ML12251A146
| ML12251A146 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/18/2010 |
| From: | Carr D G AREVA NP |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| BSEP 12-0098 51-9189033-000 | |
| Download: ML12251A146 (11) | |
Text
BSEP 12-0098 Enclosure 12 AREVA Report No. 51-9189033-000, Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietaty Version)
Controlled Document A 20004-018 (10/18/2010)
NONPROPRIETARY AREVA AREVA NP Inc.ENGINEERING INFORMATION RECORD Document No: 51 -9189033 -000 Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)Page 1 of 10 Controlled Document A AREVA 20004-018 (10/1812010) 51-9189033-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)Safety Related? M YES I-I NO Does this document contain assumptions requiring verification?
I YES NO Does this document contain Customer Required Format? [-] YES NO Signature Block Name and Title/Discipline PILP, R/LR, A/A-CRF, AIA.CRI PageslSections PreparedlReviewedl Approved or Comments Signature Date D.G. Carr, Supervisor II // P Thermal-Hydraulics Richland D.C. Serell, Engineer R A" Thermal-Hydraulics Richland fi D.W. Pruitt, Manager '-A-CRI Thermal-Hydraulics Richland ,7.A.B. Meginnis, Manager A Product Licensing
.W'1-4 ) V, > 2.1 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 PageslSectionsl Brief Description I No. Paragraphs Changed Change Authorization 000 All Initial issue of document Page 2 Controlled Document 51-9189033-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)1.0 Purpose The safety limit minimum critical power ratio (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 purpose of this report is to provide SLMCPR analysis results for Brunswick Unit 2 Cycle 21 using the Reference 1 methodology.
The results are used to demonstrate the applicability of the proposed Brunswick Unit 2 SLMCPR two-loop operation (TLO) and single-loop operation (SLO) values proposed in Reference 2 with the introduction of the Reference 1 methodology.
2.0 Methodology
The analysis presented in this document used the methodology presented in Reference
- 1. 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. []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 core loading and cycle depletion from the Brunswick Unit 2 Cycle 21 (BRK2-21) fuel cycle design was used as the basis of the SLMCPR analysis.
Figure 1 presents the core loading, including the assembly type, the cycle the fuel was originally loaded and the number of assemblies.
The BRK2-21 core is made up of ATRIUMTM 1OXM* and ATRIUM-10 fuel. Analyses were performed* ATRIUM is a trademark of AREVA NP.Page 3 Controlleu Document 51-9189033-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)[ ] for the Brunswick power/flow map for MELLLA operation as shown in Figure 2. The BSP regions shown in the power/flow map are based on the methods discussed in Reference
- 3. The radial power distribution I ] is presented in Figure 3.The ACE/ATRIUM 1OXM critical power correlation (Reference
- 4) is used for the ATRIUM 1OXM fuel while the SPCB critical power correlation (Reference
- 5) is used for the ATRIUM-1 0 fuel.The fuel- and plant-related uncertainties used in the BRK2-21 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 BRK2-21 SLMCPR analysis supports a TLO SLMCPR of 1.07 and an SLO SLMCPR of 1.09.Table 2 presents a summary of the analysis 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 3. The results are for the [I.4.0 Discussion of Results Results of the Brunswick Unit 2 Cycle 20 (BRK2-20)
SLMCPR analysis using the Reference 1 methodology are shown in Table 4. The BRK2-20 results support a TLO SLMCPR of 1.06 and an SLO SLMCPR of 1.08, 0.01 lower than the BRK2-21 results. In the AREVA methodology, the SLMCPR is iteratively increased by integer multiples of 0.01 until the percentage of rods in boiling transition is less than 0.1%. As a result, an increase of just over 0.01% to the number of rods in boiling transition calculated in the TLO BRK2-20 analysis (approximately 5 rods) would result in an increase of 0.01 in the SLMCPR result. An increase of 0.01 results in a decrease in the number of rods predicted to experience boiling transition.
The differences in the BRK2-20 and BRK2-21 SLMCPR results are consistent with expected cycle-to-cycle variations.
The BRK2-21 results continue to support the proposed Brunswick Unit 2 TLO SLMCPR of 1.08 and SLO SLMCPR of 1.11 presented in Reference 2.Page 4 Controlled Document 51-9189033-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)5.0 References
- 1. ANP-10307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011.2. Letter, M.J. Annacone (PGN) to USNRC, "Brunswick Steam Electric Plant Units Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Request for License Amendments
-Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)" and Revision to Technical Specification 2.1.1.2 Minimum Critical Power Ratio Safety Limit," BSEP 12-0031, March 2012 (NRC Accession Number ML12076A062).
- 3. 0G02-0119-260, Backup Stability Protection (BSP) for Inoperable Option Ill Solution, GE Nuclear Energy, July 17, 2002.4. ANP-10298PA Revision 0, ACE/ATRIUM IOXM Critical Power Correlation, AREVA NP, March 2010.5. EMF-2209(P)(A)
Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.6. EMF-2158(P)(A)
Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors:
Evaluation and Validation of CASMO-4 / MICROBURN-B2, Siemens Power Corporation, October 1999.7. EMF-2493(P)
Revision 0, MICROBURN-B2 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 2000.8. NEDO-1 0958-A, General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application, General Electric, January 1977.9. NEDO-20340, Process Computer Performance Evaluation Accuracy, General Electric, June 1974.10. NEDO-24344, Brunswick Steam Electric Plant Units I and 2 Single-Loop Operation, General Electric, September 1981.11. Letter, H.D. Curet (AREVA) to H.J. Richings (NRC), "POWERPLEX Core Monitoring:
Failed or Bypassed Instrumentation and Extended Calibration," HDC:96:012, May 6, 1996 (38-9043714-000).
- 12. 0B21-1305 Revision 1, "Core Monitoring LPRM Uncertainty and Sensitivity Decay," Progress Energy, March 2009 (NRC Accession Number ML092370285).
Page 5 Controlled Document 51-9189033-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)Table I Fuel- and Plant-Related Uncertainties for BRK2-21 SLMCPR Analyses Parameter Uncertainty Reference Fuel-Related Uncertainties
[]Plant-Related Uncertainties Feedwater flow rate 1.8%1 8 Feedwater temperature 0.8%t 8 Core pressure 0.8%* 9 Total core flow rate TLO 2.5% 8 SLO 6.0% 10 t Values from Reference 7 are a result of the application of the methodology discussed in Reference 11 to the base uncertainties presented in Reference
- 6. The uncertainties presented support operation with up to 50% of the LPRMs out-of-service, up to 40% of the TIP channels out-of-service, and a 2500 EFPH LPRM calibration interval.
The bases of these values include a core monitoring LPRM detector uncertainty of 4.3% from Reference 12.Referenced plant uncertainties were rounded up to the nearest 0.1% before use.The core pressure uncertainty is taken in Reference 9 to be a more conservative value than accepted in Reference 8; therefore, the more conservative value is used.Page 6 Controlled Document 51-9189033-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)Table 2 BRK2-21 Results Summary for SAFLIM3D SLMCPR Analysis Percentage of Rods SLMCPR in Boiling Transition TLO -1.07 0.085 SLO -1.09 0.075 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type Contribution of Total Rods Nuclear Predicted To Be FulFuel Burnup in BT (%)Type Design Status TLO SLO 30 ATRIUM-10 Twice burned [31 ATRIUM-10 Twice burned 33 ATRIUM 1OXM Once burned 34 ATRIUM 1OXM Once burned 35 ATRIUM 1OXM Fresh 36 ATRIUM 1OXM Fresh Table 4 BRK2-20 Results Summary for SAFLIM3D SLMCPR Analysis Percentage of Rods SLMCPR in Boiling Transition TLO -1.06 0.090 SLO -1.08 0.088 Page 7 Controlled Document 51-9189033-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)J: 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 I: 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 30 31 30 30 33 30 33 30 33 30 33 30 33 30 33 30 33 30 33 30 30 31 31 31 30 30 33 35 33 35 35 35 35 33 35 33 30 30 31 31 31 30 34 30 33 35 35 35 35 33 33 35 35 35 35 33 33 30 30 31 31 30 30 30 30 33 33 35 33 35 33 35 33 35 36 35 35 34 35 34 36 33 36 34 36 34 36 34 36 34 36 34 36 36 34 36 34 36 34 36 34 36 33 36 34 35 34 36 35 35 34 33 35 36 35 33 35 33 35 33 30 30 30 31 31 30 31 30 33 35 35 34 36 34 36 34 36 34 34 36 34 36 34 36 34 35 35 33 30 30 30 30 30 30 30 30 30 30 30 30 30 33 33 33 33 33 33 33 33 30 30 33 35 33 35 35 35 35 33 35 33 30 30 31 31 35 35 35 35 33 33 35 35 35 35 33 33 30 30 31 35 33 36 34 36 36 34 36 33 35 35 33 35 33 30 33 36 34 36 34 34 36 34 36 34 35 35 33 35 30 36 34 36 34 36 36 34 36 34 36 34 36 35 33 33 34 36 34 36 34 34 36 34 36 34 36 34 35 35 33 36 34 36 34 36 36 34 36 34 36 34 36 34 35 35 34 36 34 36 34 34 36 34 36 34 36 34 36 33 35 36 34 36 34 36 36 34 36 34 36 34 36 34 36 35 34 36 34 36 34 34 36 34 36 34 36 34 36 34 35 36 34 36 34 36 34 34 36 34 36 34 36 34 36 33 36 34 36 34 34 36 34 36 34 36 34 36 34 36 33 34 36 34 36 34 34 36 34 36 34 36 34 36 34 35 36 34 36 34 36 36 34 36 34 36 34 36 34 36 35 34 36 34 36 34 34 36 34 36 34 36 34 36 33 35 36 34 36 34 36 36 34 36 34 36 34 36 34 35 35 34 36 34 36 34 34 36 34 36 34 36 34 35 35 33 36 34 36 34 36 36 34 36 34 36 34 36 35 33 33 33 36 34 36 34 34 36 34 36 33 35 35 33 35 30 35 33 36 34 36 36 34 36 33 35 35 33 35 33 30 35 35 35 35 33 33 35 35 35 35 33 30 30 30 31 33 35 33 35 35 35 35 33 35 33 30 30 31 31 30 33 33 33 33 33 33 33 33 30 31 31 30 30 30 30 30 30 30 30 30 31 31 30 30 33 35 33 35 35 35 35 33 35 33 30 30 31 31 31 30 30 33 30 33 30 33 30 33 30 33 30 33 30 33 30 33 30 30 30 31 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 Nuclear Fuel Cycle Number of Fuel Type Description Loaded Assemblies 30 ATRIUM-10 19 84 31 ATRIUM-10 19 26 33 ATRIUM 1OXM 20 96 34 ATRIUM 1OXM 20 128 35 ATRIUM 1OXM 21 96 36 ATRIUM 1OXM 21 130 Figure 1 Brunswick Unit 2 Cycle 21 Core Loading Map Page 8 Controlled Docur<.:0 51-9189033-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)0 0.110.0 100.0 90.0 80.0 70.0 60.0 50.0 40.0 30.0 20.0 10.0 0.0 J ...... ....t 4 J,.... ........T...... .. ... ............. ............ .......... ... ..T .... ....... .::I: If. Doti] A i: .. ...... ......tht-4t. it. t L 1 1 1J.P. Rzj 101 MELLL Line BSP Manual t ljý4 14 ...... 46 Mlblh Max SLO Core+' egioLl at. Flow Natural 7 Circulation
.......H J-Mihirnurnýpower Line 36% Minlinurn P Speed U 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 Mlbslhr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 %Core Flow Figure 2 Brunswick Unit 2 Power/Flow Map With Nominal Feedwater Temperature BSP Regions Page 9 Controlled Document 51-9189033-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM31D Methodology (Nonproprietary Version)J: 1 3 4 5 6 7 8 9 10 11 12 13 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 0.267 0.351 0.400 0.422 0.429 0.429 0.422 0.399 0.351 0.275 0.354 0.502 0.682 0.742 0.778 0.796 0.794 0.777 0.741 0. 680 0.500 0.336 0.247 0.333 0.449 0.580 0.817 1.071 0.992 1.172 1.181 1.181 1.171 0.991 1.071 0.817 0.589 0.441 0.310 0.220 0.269 0.451 0.739 0.688 0.885 1.176 1.266 1.309 1.325 1.152 1.151 1.324 1.308 1.266 1.178 0.905 0.759 0.574 0.420 0.250 0.232 0.453 0.714 1.008 1.006 1.241 1.316 1.176 1.373 1.154 1.379 1.378 1.155 1.371 1.175 1.315 1.241 0.996 0.977 0.678 0.406 0.211 0.329 0.586 1.003 1.025 1.292 1.350 1.148 1.383 1.165 1.392 1.166 1.165 1.390 1.162 1.380 1.146 1.345 1.281 1.004 0.963 0.528 0.291 0.451 0.777 1.009 1.296 1.355 1.162 1.394 1.166 1.393 1.166 1.394 1.394 1. 162 1.390 1.162 1.390 1.156 1.345 1.277 0. 982 0.668 0.406 0.338 0.595 0.913 1.254 1.357 1.167 1.392 1.167 1.365 1.128 1.327 1.127 1.127 1.324 1.125 1.362 1.166 1.388 1.159 1.344 1.231 0.877 0.565 0.339 0.272 0.500 0.818 1.184 1.324 1.180 1.403 1.186 1.389 1.118 1.060 0.885 1.272 1.271 0.884 1.057 1.117 1.386 1.184 1.399 1.174 1.312 1.168 0.807 0.492 0.256 0.350 0. 678 1.070 1.266 1.174 1.385 1.175 1.404 1.170 1.317 0.892 1.024 1. 045 1.044 1.021 0.890 1.315 1.169 1.403 1.173 1.382 1.169 1.257 1.061 0.672 0.347 0.397 0.735 0.985 1.300 1.365 1.151 1.388 1.166 1.384 1.135 1.273 1.042 1.238 1.235 1.039 1.269 1.133 1.384 1 .167 1.388 1.151 1.362 1.296 0.979 0.731 0.394 0.418 0.768 1.159 1.305 1.124 1.336 1.107 1.326 1.138 1.356 1.103 1.273 1.035 1.029 1.262 1.100 1.356 1.141 1.328 1.108 1.338 1.124 1.303 1. 155 0.766 0.416 0.425 0.786 1.165 1.124 1.324 1.073 1.044 0.888 1.315 1.134 1.310 1.058 1.237 1.026 1.052 1.309 1.135 1.318 0.891 1.046 1.076 1.325 1.124 1.162 0.784 0.424 1 2 3 4 5 6 7 10 11 12 13 J:14 15 16 17 18 19 20 21 22 23 24 25 26 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 0.429 0.788 1.165 1.127 1.323 1.073 1.043 0.889 1.314 1.133 1.307 1.052 1.026 1.237 1.058 1.312 1.136 1.318 0.890 1.047 1.077 1.326 1.124 1.162 0.784 0.423 0.422 0.774 1.160 1.304 1.123 1.334 1.106 1.324 1.137 1.352 1.098 1.260 1.028 1.035 1.273 1.104 1.358 1.141 1.329 1.109 1.339 1.126 1.304 1.155 0.766 0.416 0.402 0.742 0.986 1.297 1.360 1.148 1.384 1.165 1.380 1.131 1.266 1.038 1.233 1.236 1.044 1.273 1.135 1.386 1.168 1.389 1.151 1.363 1.296 0.979 0.731 0.395 0.357 0.694 1.071 1.260 1.160 1.377 1.173 1.398 1.166 1.311 0.888 1.018 1.042 1.043 1.023 0.892 1.317 1.169 1.404 1.174 1.382 1.167 1.258 1.061 0.673 0.347 0.279 0.504 0.819 1.177 1.314 1.146 1.395 1.181 1.381 1.113 1.053 0.881 1.267 1.269 0.885 1.059 1.119 1.387 1.184 1.399 1.173 1.312 1.168 0.807 0.493 0.268 0.352 0.592 0.908 1.242 1.345 1.158 1.383 1.162 1.357 1.121 1.319 1.123 1.123 1.324 1.127 1.364 1.164 1.388 1.158 1.344 1.231 0.878 0.564 0.327 0.446 0.767 0.998 1.283 1.343 1.153 1.385 1.160 1.385 1.163 1.389 1.390 1.160 1.391 1.165 1.391 1.157 1.345 1.278 0.983 0.670 0.406 0.313 0.575 0. 984 1.010 1.280 1.341 1.143 1.376 1.159 1.386 1.163 1.164 1.389 1.162 1.381 1.147 1.344 1.280 1.006 0.964 0.536 0.291 0.223 0.425 0.687 0.979 0.993 1.236 1.311 1.172 1.367 1.151 1.375 1.376 1.156 1.371 1.177 1.315 1.239 0.993 0.975 0.678 0.406 0.208 0.254 0.432 0.550 0.753 0.890 1.173 1.262 1.306 1.322 1.149 1.153 1.325 1.309 1.266 1.177 0. 902 0. 755 0.565 0.418 0.243 0.224 0.306 0.439 0.577 0.814 1.069 0.991 1.170 1.181 1.181 1.172 0.994 1.072 0.817 0.579 0.425 0.307 0.221 0.333 0.499 0.680 0.740 0.777 0.796 0.796 0.779 0.743 0.682 0.500 0.333 0.274 0.350 0.398 0.421 0.429 0.430 0.422 0.400 0.349 0.274 14 15 16 17 18 19 20 21 22 23 24 25 26 Figure 3 Radial Power Distribution for Brunswick Unit 2 Cycle 21 SLMCPR[ I Page 10