BSEP 12-0098, Enclosure 15 to BSEP 12-0098, Areva Report No. 51-9189034-000, Brunswick Unit 2 Cycle 21 SLMCPR Analysis with SAFLIM3D Methodology - Operability Assessment

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Enclosure 15 to BSEP 12-0098, Areva Report No. 51-9189034-000, Brunswick Unit 2 Cycle 21 SLMCPR Analysis with SAFLIM3D Methodology - Operability Assessment
ML12251A147
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 10/18/2010
From: Carr D
AREVA NP
To:
Office of Nuclear Reactor Regulation
References
BSEP 12-0098 51-9189034-000
Download: ML12251A147 (11)
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BSEP 12-0098 Enclosure 15 AREVA Report No. 51-9189034-000, Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology -

OperabilityAssessment (NonproprietaryVersion)

(,,'on tro Iled m~c rentL A

20004-018 (1011812010)

NONPROPRIETARY AREVA AREVA NP Inc.

ENGINEERING INFORMATION RECORD Document No: 51 - 9189034 - 000 Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version)

Page 1 of 10

Controlled Document A 20004-018 (1011812010) 51-9189034-000 AREVA NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version)

Safety Related? Z,ýjYES17LI NO Does this document contain assumptions requiring verification? [] YES MNO Does this document contain Customer Required Format? [-] YES M NO Signature Block PILP, R/LR, PageslSections Name and A/A-CRF, PreparedlReviewedl TitlelDiscipline Signature AIA-CRI Date Approved or Comments D.G. Carr, Supervisor " I _' P Thermal-Hydraulics Richland D.C. Serell, Engineer R Thermal-Hydraulics Richland D.W. Pruitt, Manager <E -CRI Ad Thermal-Hydraulics Richland A.B. Meginnis, Manager A 4

yr.A Product Licensing _ _ * ,, _ __/

Note: P/LP designates Preparer (P), Lead Preparer (LP)

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

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

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

Record of Revision Revision PageslSections/ Brief Description I No. Paragraphs Changed Change Authorization 000 All Initial issue of document Page 2

Controlled Document 51-9189034-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version) 1.0 Purpose Reference 1 presents results of the Brunswick Unit 2 Cycle 21 (BRK2-21) safety limit minimum critical power ratio (SLMCPR) analysis using the currently approved Reference 2 ACE/ATRIUMTM 1OXM*

critical power correlation. As discussed in Reference 3, 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 3.

The purpose of this report is to present results of an operability assessment for the BRK2-21 SLMCPR calculations presented in Reference 1 using the updated critical power correlation described in Reference 3 for the ATRIUM 1OXM fuel. The results of this analysis are used to demonstrate the applicability of the Brunswick Unit 2 SLMCPR two-loop operation (TLO) and single-loop operation (SLO) values proposed in Reference 4 with the introduction of the Reference 1 methodology. The approach used in this operability assessment is consistent with the licensing condition proposed in Reference 4.

2.0 Methodology The analysis presented in this document used the methodology presented in Reference 5 and the operability assessment critical power correlation presented in Reference 3 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.

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Controlled Document 51-9189034-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 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 5 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 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 6. 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 7) is used for the ATRIUM-10 fuel.

The fuel- and plant-related uncertainties used in the BRK2-21 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 BRK2-21 SLMCPR operability assessment analysis supports a TLO SLMCPR of 1.06 and an SLO SLMCPR of 1.08. 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 1 based on the currently approved ACE/ATRIUM 1OXM critical power correlation (Reference 2) are presented in Table 4. They are based on the same BRK2-21 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- [ ]. The other major difference is the application of the improved K-factor methodology described in Reference 3.

The results show that the operability assessment supports TLO and SLO SLMCPR values 0.01 less than the Reference 1 analysis. Overall, the Reference 1 results and the operability assessment results Page 4

Controlled Document 51-9189034-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version) reported herein continue to support the proposed Brunswick Unit 2 TLO SLMCPR of 1.08 and SLO SLMCPR of 1.11 presented in Reference 4.

5.0 References

1. 51-9186363-000, "Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology (Proprietary Version)," AREVA NP, August 2012.
2. ANP-10298PA Revision 0, ACE/ATRIUM IOXM CriticalPower Correlation,AREVA NP, March 2010.
3. ANP-3086(P) Revision 0, Brunswick Unit 1 and Unit 2 SLMCPR OperabilityAssessment Critical Power Correlationfor ATRIUM IOXM Fuel - Improved K-factor Model, AREVA NP, February 2012.
4. 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).
5. ANP-1 0307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011.
6. 0G02-0119-260, Backup Stability Protection (BSP) for Inoperable Option III Solution, GE Nuclear Energy, July 27, 2002.
7. EMF-2209(P)(A) Revision 3, SPCB CriticalPower Correlation,AREVA NP, September 2009.
8. 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.
9. EMF-2493(P) Revision 0, MICROBURN-B2 Based Impact of Failed/BypassedLPRMs and TIPs, Extended LPRM CalibrationInterval, and Single Loop Operationon Measured Radial Bundle Power Uncertainty, Siemens Power Corporation, December 2000.
10. NEDO-1 0958-A, General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlationand Design Application, General Electric, January 1977.
11. NEDO-20340, Process Computer Performance Evaluation Accuracy, General Electric, June 1974.
12. NEDO-24344, Brunswick Steam Electric Plant Units I and 2 Single-Loop Operation, General Electric, September 1981.
13. 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).
14. 0B21-1305 Revision 1, "Core Monitoring LPRM Uncertainty and Sensitivity Decay,"

Progress Energy, March 2009 (NRC Accession Number ML092370285).

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Controlled Document 51-9189034-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version)

Table 1 Fuel- and Plant-Related Uncertainties for BRK2-21 SLMCPR Analyses Parameter Uncertainty Reference Fuel-RelatedUncertainties

[

]

Plant-RelatedUncertainties Feedwater flow rate 1.8%* 10 Feedwater temperature 0.8%t 10 Core pressure 0.8%t' § 11 Total core flow rate TLO 2.5% 10 SLO 6.0% 12 I

t Values from Reference 9 are a result of the application of the methodology discussed in Reference 13 to the base uncertainties presented in Reference 8. 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 14.

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

§ The core pressure uncertainty is taken in Reference 11 to be a more conservative value than accepted in Reference 10; therefore, the more conservative value is used.

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Controlled Document 51-9189034-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version)

Table 2 BRK2-21 Results Summary for SLMCPR Analysis (Operability Assessment CPR Correlation for ATRIUM IOXM)

Percentage of Rods SLMCPR in Boiling Transition TLO - 1.06 0.063 SLO - 1.08 0.077 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type Contribution of Total Rods Nuclear Fuel Fuel Burnup Predicted To Be in BT (%)

Type Design Status TLO SLO 30 ATRIUM-10 Twice burned [

31 ATRIUM-10 Twice burned 33 ATRIUM 10XM Once burned 34 ATRIUM 10XM Once burned 35 ATRIUM 1OXM Fresh 36 ATRIUM 10XM Fresh Table 4 BRK2-21 Results Summary for SLMCPR Analysis (Reference 2 ACE/ATRIUM 10XM CPR Correlation)

Percentage of Rods SLMCPR in Boiling Transition TLO - 1.07 0.085 SLO - 1.09 0.075 Page 7

Controlled Document 51-9189034-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D 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 I:

1 30 30 30 30 30 30 30 30 30 30 2 31 30 33 33 33 33 33 33 33 33 30 30 3 31 30 30 30 33 35 33 35 35 35 35 33 35 33 30 30 31 31 4 31 30 30 33 33 35 35 35 35 33 33 35 35 35 35 33 33 30 30 31 5 31 30 33 35 33 35 35 33 36 34 36 36 34 36 33 35 35 33 35 33 30 31 6 31 34 35 33 35 35 33 36 34 36 34 34 36 34 36 34 35 35 33 35 30 31 7 30 30 33 35 36 34 36 34 36 34 36 36 34 36 34 36 34 36 35 33 33 30 8 30 30 33 35 35 34 36 34 36 34 36 34 34 36 34 36 34 36 34 35 35 33 30 31 9 31 30 33 35 35 34 36 34 36 34 36 34 36 36 34 36 34 36 34 36 34 35 35 33 30 30 10 30 33 35 35 33 36 34 36 34 36 34 36 34 34 36 34 36 34 36 34 36 33 35 35 33 30 11 30 33 33 35 36 34 36 34 36 34 36 34 36 36 34 36 34 36 34 36 34 36 35 33 33 30 12 30 33 35 35 34 36 34 36 34 36 34 36 34 34 36 34 36 34 36 34 36 34 35 35 33 30 13 30 33 35 33 36 34 36 34 36 34 36 34 36 34 34 36 34 36 34 36 34 36 33 35 33 30 14 30 33 35 33 36 34 36 34 36 34 36 34 34 36 34 36 34 36 34 36 34 36 33 35 33 30 15 30 33 35 35 34 36 34 36 34 36 34 36 34 34 36 34 36 34 36 34 36 34 35 35 33 30 16 30 33 33 35 36 34 36 34 36 34 36 34 36 36 34 36 34 36 34 36 34 36 35 33 33 30 17 30 33 35 35 33 36 34 36 34 36 34 36 34 34 36 34 36 34 36 34 36 33 35 35 33 30 18 30 30 33 35 35 34 36 34 36 34 36 34 36 36 34 36 34 36 34 36 34 35 35 33 30 30 19 31 30 33 35 35 34 36 34 36 34 36 34 34 36 34 36 34 36 34 35 35 33 30 31 20 30 33 33 35 36 34 36 34 36 34 36 36 34 36 34 36 34 36 35 33 33 30 21 31 30 35 33 35 35 33 36 34 36 34 34 36 34 36 33 35 35 33 35 30 31 22 31 30 33 35 33 35 35 33 36 34 36 36 34 36 33 35 35 33 35 33 30 31 23 31 30 30 30 33 35 35 35 35 33 33 35 35 35 35 33 30 30 30 31 24 31 31 30 30 33 35 33 35 35 35 35 33 35 33 30 30 31 31 25 30 30 33 33 33 33 33 33 33 33 30 31 26 31 30 30 30 30 30 30 30 30 30 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 10XM 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 Docu:ment 51-9189034-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version) 110.0 100.0 1'T t ifd: Tr!V-T.~

ij d 90.0 80.0 70.0 60.0 0

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.jJ 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/hr 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 51-9189034-000 NONPROPRIETARY Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version)

J: 1 2 3 4 5 6 7 8 9 10 11 12 13 0.273 0.352 0.398 0.420 0.427 2 0.340 0.503 0.681 0.738 0.772 0.789 3 0.233 0.331 0.453 0.598 0.823 1.075 0.989 1.163 1.169 4 0.271 0.456 0.589 0.782 0.919 1.190 1.272 1.306 1.310 1.128 5 0.248 0.454 0.718 1.008 1.015 1.261 1.332 1.180 1.371 1.127 1.326 6 0.335 0.744 1.013 1.032 1.304 1.366 1.187 1.392 1.154 1.336 1.067 7 0.452 0.692 1.012 1.300 1.363 1.173 1.411 1.178 1.389 1.101 1.009 8 0.356 0.583 0.890 1.249 1.358 1.168 1.399 1.190 1.407 1.165 1.317 0.858 9 0.268 0.504 0.822 1.183 1.324 1.155 1.401 1.170 1.389 1.168 1.380 1.131 1.303 10 0.353 0.686 1.077 1.274 1.184 1.391 1.169 1.364 1.110 1.306 1.127 1.349 1.128 11 0.403 0.746 0.999 1.318 1.382 1.170 1.3 95 1.120 1.021 0.858 1.259 1.096 1.305 12 0.424 0.783 1.179 1.334 1.161 1.398 1.166 1.316 0.851 0.982 1.028 1.264 1.052 13 0.432 0.802 1.189 1.160 1.388 1.170 1.395 1.119 1.253 1.027 1.223 1.027 1.231 14 0.432 0.799 1.189 1.158 1.387 1.169 1.394 1.119 1.252 1.026 1.220 1.020 1.020 15 0.424 0.782 1.178 1.333 1.162 1.396 1.162 1.313 0.849 0.978 1.025 1.253 1.045 16 0.401 0.746 0.998 1.317 1.380 1.167 1.392 1.117 1.018 0.855 1.254 1.092 1.303 17 0.353 0.685 1.077 1.273 1.182 1.388 1.165 1.360 1.108 1.303 1.124 1.348 1.128 18 0.276 0.503 0.822 1.185 1.323 1.153 1.397 1.168 1.386 1.166 1.378 1.133 1.305 19 0.339 0.592 0.911 1.248 1.352 1.161 1.394 1.186 1.404 1.164 1.318 0.859 20 0.444 0.764 1.002 1.288 1.352 1.164 1.405 1.176 1.389 1.100 1.010 21 0.312 0.577 0.982 1.010 1.284 1.351 1.179 1.387 1.152 1.336 1.069 22 0.222 0.422 0.682 0.967 0.987 1.236 1.318 1.174 1.367 1.125 1.326 23 0.251 0.408 0.530 0.671 0.881 1.172 1.262 1.300 1.307 1.126 24 0.212 0.292 0.408 0.567 0.810 1.064 0.982 1.158 1.165 25 0.341 0.493 0.675 0.733 0.768 0.786 26 0.257 0.347 0.395 0.417 0.424 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 0.431 0.424 0.404 0.359 0.280 2 0.791 0.778 0.746 0.698 0.507 0.353 3 1.170 1.164 0.991 1.075 0.824 0.595 0.448 0.315 0.224 4 1.131 1.309 1.303 1.267 1.183 0.913 0.772 0.578 0.427 0.255 5 1.326 1.126 1.366 1.166 1.322 1.250 1.005 0.990 0.692 0.434 0.225 6 1.067 1.334 1.151 1.384 1.153 1.354 1.291 1.017 0.985 0.553 0.308 7 1.009 1.099 1.386 1.177 1.402 1.164 1.352 1.288 0.999 0.758 0.442 8 0.858 1.315 1.163 1.401 1.184 1.391 1.159 1..350 1.245 0.896 0.581 0.335 9 1.302 1.130 1.376 1.164 1.382 1.165 1.393 1.150 1.320 1.181 0.819 0.502 0.275 10 1.127 1.345 1.123 1.300 1.105 1.356 1.164 1.384 1.180 1.271 1.076 0.684 0.352 11 1.302 1.091 1.252 0.854 1.014 1.115 1.388 1.165 1.377 1.315 0.998 0.746 0.401 12 1.046 1.252 1.023 0.976 0.847 1.309 1.164 1.393 1.158 1.332 1.178 0.782 0.424 13 1.020 1.020 1.218 1.025 1.249 1.116 1.390 1.168 1.385 1.157 1.188 0.801 0.431 14 1.231 1.027 1.222 1.025 1.250 1.116 1.391 1.169 1.386 1.161 1.189 0.802 0.432 15 1.052 1.264 1.029 0.980 0.850 1.313 1.160 1.396 1.163 1.334 1.180 0.785 0.425 16 1.305 1.096 1.258 0.857 1.020 1.119 1.393 1.167 1.380 1.318 1.000 0.748 0.403 17 1.128 1.350 1.126 1.305 1.110 1.362 1.168 1.389 1.185 1.274 1.078 0.687 0.351 18 1.305 1.133 1.380 1.166 1.387 1.167 1.398 1.154 1.323 1.184 0.822 0.503 0.275 19 0.859 1.319 1.165 1.405 1.186 1.394 1.162 1.352 1.247 0.908 0.582 0.335 20 1.010 1.101 1.389 1.176 1.405 1.163 1.352 1.287 0.999 0.760 0.427 21 1.070 1.336 1.153 1.388 1.179 1.351 1.284 1.012 0.979 0.568 0.309 22 1.326 1.127 1.368 1.171 1.318 1.237 0.988 0.968 0.682 0.420 0.223 23 1.125 1.307 1.300 1.262 1.172 0.882 0.673 0.538 0.408 0.245 24 1.165 1.158 0.982 1.064 0.810 0.566 0.407 0.292 0.209 25 0.786 0.768 0.733 0.675 0.494 0.328 26 0.423 0.416 0.395 0.348 0.269 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[]

With Operability Assessment CPR Correlation Page 10

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