ML12251A145
| ML12251A145 | |
| 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 51-9177315-001 | |
| Download: ML12251A145 (11) | |
Text
{{#Wiki_filter:BSEP 12-0098 Enclosure 9 AREVA Report No. 51-9177315-001, Brunswick Unit I Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology -Operability Assessment (Nonproprietary Version) Controlled Docwmurent A AREVA 20004-018 (10/18/2010) AREVA NP Inc.ENGINEERING INFORMATION RECORD Document No: 51 -9177315 -001 Brunswick Unit I Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology -Operability Assessment (Nonproprietary Version)Page 1 of 10 ContrK-{ D ocurnen A AREVA 20004-018 (10/18/2010) 51-9177315-001 Brunswick Unit I Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology -Operability Assessment (Nonproprietary Version)Safety Related?Z YES F-1NO Does this document contain assumptions requiring verification? I YES M NO Does this document contain Customer Required Format? [ YES ý] NO Signature Block Name and Title/Discipline D.G. Carr, Supervisor Thermal-Hydraulics Richland D.R. Tinkler, Engineer Thermal-Hydraulics Richland D.W. Pruitt, Manager Thermal-Hydraulics Richland A.B. Meginnis, Manager Product Licensing PageslSections Prepared/Reviewedl Approved or Comments I1 I.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)A/A-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.001 Page 5 Updated Reference 7 to Revision 1.I Page 10, Figure 3 Updated rated power distribution. Changes are further identified by a vertical bar in the right-hand margin.Page 2 Controlled Document 51-9177315-001 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology -Operability Assessment (Nonproprietary Version)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 and 4), a realistic fuel channel bow model (Reference 5), and expanded coupling with the MICROBURN-B2 core simulator (Reference 6). More detailed descriptions of these improvements are discussed in Reference 1.Reference 7 presents results of the Brunswick Unit 1 Cycle 19 (BRK1-19)
SLMCPR analysis using the currently approved Reference 4 ACE/ATRIUMTM 1OXM* critical power correlation. As discussed in Reference 8, a concern was identified in the calculation of the K-factor within the approved ACE/ATRIUM 1OXM correlation. The K-factor methodology was modified in response to the deficiencies found in the axial averaging process. An updated correlation for use in the Brunswick SLMCPR operability assessment calculations with ATRIUM 1OXM fuel is described in Reference 8.The purpose of this report is to present results of an operability assessment for the BRK1-19 SLMCPR calculations presented in Reference 7 using the updated critical power correlation described in Reference 8 for the ATRIUM 1OXM fuel. The results of this analyses 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 and the operability assessment critical power correlation presented in Reference 8 for the ATRIUM 1OXM fuel.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. [* ATRIUM is a trademark of AREVA NP.Page 3 Controlled Document 51-9177315-001 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology -Operability Assessment (Nonproprietary Version)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 BRK1-19 fuel cycle design report (Reference
- 9) 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 BRK1-19 core is made up of ATRIUM 1OXM and ATRIUM-10 fuel. Analyses were performed [] 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
- 10. The radial power distribution
[] is presented in Figure 3.The operability assessment critical power correlation is used for the ATRIUM 1OXM fuel while the SPCB critical power correlation (Reference
- 11) is used for the ATRIUM-10 fuel.The fuel- and plant-related uncertainties used in the BRK1-19 SLMCPR analysis are presented in Table 1. The radial and nodal power uncertainty 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 BRK1-19 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 []4.0 Discussion of Results Results from Reference 7 based on the currently approved ACE/ATRIUM 1OXM critical power correlation (Reference
- 4) are presented in Table 4. They are based on the same BRK1-19 design step-through and most of the same fuel- and plant-related uncertainties.
The one exception is a slightly higher additive constant uncertainty associated with the currently approved correlation for the ATRIUM 1OXM fuel- [ ]. A comparison of results shows Page 4 Controlled Document 51-9177315-001 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology -Operability Assessment (Nonproprietary Version)a decrease in the number of rods expected to experience boiling transition in both TLO and SLO with the use of the operability assessment correlation. The same SLMCPR limits are supported with both the currently approved ACE correlation (Reference
- 4) and the operability assessment correlation.
5.0 References
- 1. ANP-1 0307PA 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 Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.3. ANP-10249PA Revision 1, ACE/ATRIUM-IO Critical Power Correlation, AREVA NP, September 2009.4. ANP-10298PA Revision 0, ACE/ATRIUM IOXM Critical Power Correlation, AREVA NP, March 2010.5. BAW-1 0247PA Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP, February 2008.6. 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. 51-9175814-001, "Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Proprietary Version)," AREVA NP, July 2012.8. ANP-3086(P), Brunswick Unit 1 and Unit 2 SLMCPR Operability Assessment Critical Power Correlation for ATRIUM IOXM Fuel -Improved K-factor Model, AREVA NP, February 2012.9. ANP-3005(P) Revision 0, Brunswick Unit I Cycle 19 Fuel Cycle Design, AREVA NP, June 2011.10. 0G02-0119-260, Backup Stability Protection (BSP) for Inoperable Option lll,"GE Nuclear Energy, July 27, 2002.11. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.12. EMF-2493(P), MICROBURN-B2 Based Impact of Failed/Bypassed LPRMs and TIPs, Extended LPRM Calibration Interval, and Single Loop Operation on Measured Radial Bundle Power Uncertainty, AREVA NP, December 2000.13. NEDO-20340, Process Computer Performance Evaluation Accuracy, General Electric, June 1974.14. NEDO-1 0958-A, General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application, General Electric, January 1977.15. NEDO-24344, Brunswick Steam Electric Plant Units I and 2 Single-Loop Operation, General Electric, September 1981.16. 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).
- 17. 0B21-1305 Revision 1, "Core Monitoring LPRM Uncertainty and Sensitivity Decay," Progress Energy, March 2009 (NRC Accession Number ML092370285).
Page 5 Controlled Document 51-9177315-001 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology -Operability Assessment (Nonproprietary Version)Table I Fuel- and Plant-Related Uncertainties for BRKI-19 SLMCPR Analyses Parameter Uncertainty Reference Fuel-Related Uncertainties [Plant-Related Uncertainties Feedwater flow rate 1.8%* 14 Feedwater temperature 0.8%1 14 Core pressure 0.8%1, § 13 Total core flow rate TLO 2.5% 14 SLO 6.0% 15 t Values from Reference 12 are a result of the application of the methodology discussed in Reference 16 to the base uncertainties presented in Reference
- 6. The uncertainties presented support operation with up to 50% of 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 17.Referenced plant uncertainties were rounded up to the nearest 0.1% before use.The core pressure uncertainty is taken in Reference 13 to be a more conservative value than accepted in Reference 14; therefore, the more conservative value is used.Page 6 Controlled Document 51-9177315-001 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology -Operability Assessment (Nonproprietary Version)Table 2 BRK1-19 Results Summary for SLMCPR Analysis (Operability Assessment CPR Correlation for ATRIUM 1OXM)Percentage of Rods SLMCPR in Boiling Transition TLO -1.07 0.051 SLO -1.09 0.053 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type Contribution of Total Rods Nuclear Predicted To Be Fuel Fuel Burnup in BT (%)Type Design Status TLO SLO 30 ATRIUM-10 Twice burned [31 ATRIUM-10 Twice burned 32 ATRIUM-10 Once burned 33 ATRIUM-10 Once burned 34 ATRIUM 1OXM Fresh 35 ATRIUM 1OXM Fresh ]Table 4 BRKI-19 Results Summary for SLMCPR Analysis (Reference 4 ACE/ATRIUM 1OXM CPR Correlation) Percentage of Rods SLMCPR in Boiling Transition TLO- 1.07 0.073 SLO -1.09 0.083 Page 7 Controlled Document 51-9177315-001 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM31D Methodology -Operability Assessment (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 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 31 30 32 31 32 30 32 30 32 30 32 31 32 30 32 30 32 31 32 30 32 31 31 31 30 30 32 30 32 32 34 32 34 34 34 33 34 34 34 34 33 34 33 34 34 33 34 34 34 32 34 32 34 30 32 30 32 31 31 31 31 30 31 31 32 32 32 34 33 34 32 34 33 34 35 34 34 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 34 34 33 33 34 35 34 32 34 32 34 33 30 32 32 31 30 31 31 31 30 30 31 30 30 30 31 31 30 32 32 32 32 32 32 32 32 32 32 31 32 32 34 33 34 34 34 34 33 34 32 32 31 30 31 34 34 34 34 34 33 33 34 34 34 34 34 32 32 30 31 34 35 33 35 33 35 35 33 35 33 35 34 33 34 32 30 34 33 35 33 35 33 33 35 33 35 33 34 34 32 34 32 33 35 33 35 33 35 35 33 35 33 35 33 35 34 33 32 35 33 35 33 35 33 33 35 33 35 33 35 33 34 34 34 33 35 33 35 33 35 35 33 35 33 35 33 35 33 35 34 35 33 35 33 35 33 33 35 33 35 33 35 33 35 33 34 33 35 33 35 33 35 35 33 35 33 35 33 35 33 35 34 35 33 35 33 35 33 33 35 33 35 33 35 33 35 33 34 33 35 33 35 33 33 35 33 35 33 35 33 35 33 35 33 33 35 33 35 33 35 33 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 33 35 33 35 33 35 33 35 33 34 33 35 33 35 33 35 35 33 35 33 35 33 35 33 35 34 35 33 35 33 35 33 33 35 33 35 33 35 33 35 33 34 33 35 33 35 33 35 35 33 35 33 35 33 35 33 35 34 35 33 35 33 35 33 33 35 33 35 33 35 33 34 34 34 33 35 33 35 33 35 35 33 35 33 35 33 35 34 33 32 34 33 35 33 35 33 33 35 33 35 33 34 34 32 34 32 34 35 33 35 33 35 35 33 35 33 35 34 33 34 32 30 34 34 34 34 34 33 33 34 34 34 34 34 32 32 30 31 32 32 34 33 34 34 34 34 33 34 32 32 31 30 31 31 32 32 32 32 32 32 32 32 32 32 31 31 31 31 30 30 31 30 30 31 30 31 31 31 32 32 34 33 34 34 34 34 33 34 32 32 31 30 31 31 32 32 32 32 32 32 32 32 32 32 31 30 31 30 31 30 30 31 30 31 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 17 38 31 ATRIUM-10 17 46 32 ATRIUM-10 18 80 33 ATRIUM-10 18 162 34 ATRIUM IOXM 19 96 35 ATRIUM 1OXM 19 138 Figure I Brunswick Unit 1 Cycle 19 Core Loading Map Page 8 Controileu [ oD a 51-9177315-001 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology -Operability Assessment (Nonproprietary Version)110.0 100.0 90.0 80.0 70.0 I 0 IL 60.0 50.0 40.0 30.0 20.0 10.0 0.0 t 1 4.I~ rA .S ~~tti I ~4Ul~ 36 Min~um Pup Sped 4~ M~n~mRn oe Ln 1 iLL:i ni 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/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow Figure 2 Brunswick Unit I Power/Flow Map With Nominal Feedwater Temperature BSP Regions Page 9 Controlled Document 51-9177315-001 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology -Operability Assessment (Nonproprietary Version)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 J: 1 0.322 0.383 0.398 0.424 0.426 0.435 0.425 0.396 0.374 0.321 2 3 4 5 6 7 8 9 10 11 12 13 0,425 0,616 o0710 0,747 0,776 0,794 0,792 0,776 0,745 0,708 0,614 0,425 0.271 0.368 0.512 0.733 0.872 1.096 0.935 1.153 1.159 1.159 1.153 0.934 1.094 0.870 0.733 0.511 0.380 0.266 0.311 0.486 0.693 0.829 1.114 1.221 1.269 1.290 1.294 1.078 1.078 1.293 1.288 1.267 1.218 1.112 0.826 0.690 0.481 0.304 0.279 0.484 0.765 1.042 0.975 1.275 1.323 1.122 1.346 1.118 1.343 1.343 1.117 1.344 1.119 1.320 1.271 0.964 1.038 0.762 0.483 0.269 0.384 0.692 1.040 1.043 1.298 1.350 1.142 1.362 1.130 1.351 1.127 1.127 1.349 1.128 1.358 1.139 1.346 1.294 1.042 1.036 0.689 0.379 0.517 0.827 0.965 1.298 1.351 1.143 1.384 1.144 1.354 1.123 1.322 1.321 1.121 1.351 1.132 1.380 1.143 1.346 1.293 0.961 0.820 0.500 0.416 0.735 1.117 1.277 1.353 1.147 1.373 1.153 1.336 1.073 1.263 1.049 1.050 1.261 1.071 1.332 1.148 1.368 1.142 1.347 1.272 1.1il 0.730 0.409 0.325 0.617 0.874 1.227 1.329 1.141 1.380 1.145 1.344 1.052 0.984 0.811 1.190 1.190 0.810 0.983 1.054 1.339 1.141 1.373 1.131 1.323 1.221 0.869 0.614 0.322 0.376 0.712 1.103 1.279 1.121 1.369 1.147 1.359 1.099 1.245 0.807 0.945 0.966 0.968 0.946 0.816 1.243 1.092 1.353 1.140 1.362 1.115 1.274 1.099 0.709 0.376 0.416 0.757 0.943 1.301 1.361 1.135 1.358 1.107 1.299 1.041 1.199 0.980 1.212 1.215 0.984 1.201 1.040 1.295 1.104 1.352 1.130 1.355 1.296 0.939 0.755 0.409 0.430 0.786 1.163 1.302 1.116 1.330 1.069 1.276 1.050 1.265 1.033 1.228 1.014 1.025 1.238 1.038 1.263 1.054 1.270 1.061 1.324 1.110 1.296 1.159 0.783 0.428 0.437 0.801 1.167 1.076 1.325 1.060 1.028 0.848 1.240 1.053 1.267 1.024 1.017 1.244 1.030 1.267 1.051 1.236 0.845 1.023 1.056 1.319 1.074 1.164 0.800 0.442 1 2 3 4 5 6 7 8 9 10 11 12 13 J: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 0.439 0.799 1.166 1.075 1.325 1.060 1.028 0.848 1.241 1.054 1.271 1.031 1.245 1.015 1.022 1.265 1.049 1.236 0.843 1.024 1.055 1.320 1.072 1.164 0.797 0.439 0,433 0.783 1.162 1,301 1,331 1.070 1.279 1,052 1.270 1.037 1.243 1.025 1.017 1.229 1.032 1.264 1.047 1.272 1.065 1.326 1.1il 1.298 1.160 0.782 0.433 0.411 0.754 0.940 1.301 1.362 1.135 1.362 1.114 1.304 1.044 1.207 0.986 1.219 1.216 0.979 1.200 1.038 1.298 1.105 1.356 1.128 1.358 1.298 0.937 0.754 0.418 0.380 0.711 1.103 1.280 1.120 1.372 1.142 1.364 1.105 1.252 0.813 0.951 0.970 0.969 0.948 0.814 1.247 1.093 1.358 1.136 1.368 1.116 1.278 1.103 0.711 0.380 0.329 0.616 0.874 1.228 1.332 1.142 1.384 1.148 1.350 1.050 0.989 0.814 1.197 1.196 0.812 0.986 1.054 1.345 1.144 1.380 1.140 1.331 1.228 0.874 0.617 0.332 0.429 0.735 1.118 1.280 1.356 1.148 1.378 1.154 1.342 1.076 1.271 1.054 1.053 1.269 1.073 1.339 1.152 1.375 1.145 1.355 1.281 1.119 0.734 0.429 0.518 0.828 0.967 1.301 1.354 1.146 1.389 1.145 1.361 1.125 1.331 1.331 1.125 1.359 1.136 1.387 1.145 1.354 1.302 0.976 0.828 0.518 0.392 0.693 1.041 1.044 1.300 1.353 1.142 1.369 1.133 1.360 1.130 1.130 1.359 1.132 1.367 1.141 1.354 1.301 1.044 1.043 0.693 0.387 0.273 0.484 0.764 1.040 0.964 1.276 1.327 1.123 1.353 1.121 1.352 1.352 1.121 1.352 1.122 1.326 1.276 0.964 1.042 0.765 0.487 0.271 0.308 0.484 0.691 0.825 1.113 1.222 1.273 1.295 1.300 1.081 1.082 1.300 1.295 1.273 1.222 1.114 0.826 0.692 0.483 0.308 0.270 0.380 0.517 0.731 0.869 1.097 0.936 1.158 1.165 1.165 1.159 0.936 1.097 0.870 0.731 0.512 0.384 0.272 0.422 0.612 0.706 0.750 0.779 0.796 0.797 0.779 0.751 0.706 0.613 0.421 0.323 0.376 0.405 0.440 0.435 0.435 0.439 0.405 0.376 0.321 14 15 16 17 18 19 20 21 22 23 24 25 26 Figure 3 Radial Power Distribution for Brunswick Unit I Cycle 19 SLMCPR[ ]With Operability Assessment CPR Correlation Page 10}}