ML15282A222
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ATTACHMENT 33 FS1-0019630, Browns Ferry Unit 3 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology (Non-Proprietary)
IDENTIFICATION REVISION I
FS1-0019630 11 1.0 I
AREVA Front End BG A
Fuel BU AREVA TOTAL NUMBER OF PAGES: 18 Browns Ferry Unit 3 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology ADDITIONAL INFORMATION:
BFE3 Cycle 19 PROJECT DISTRIBUTION TO PURPOSE OF DISTRIBUTION HANDLING Restricted AREVA CATEGORY EIR - Engineering Information Report 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: 09012167806b9cb0 Role Name Writer WANG Peng Writer MOOSE James Reviewer TYLINSKI Scott Reviewer TOUVANNAS George Approver MEGINNIS Alan Approver SCHNEPP Robert RELEASE DATA:
SAFETY RELATED DOCUMENT:
y CHANGE CONTROL RECORDS:
France:
N This document, when revised, must be USA:
y reviewed or approved by the following regions:
Germany:
N
- Release date (YYYY/MM/DD) : 2015/03/25 16:24:36
[Western European Time]
Date (YYYY/MM/DD) 2015/03/25 00:00:23 2015/03/24 23:43:23 2015/03/25 00:27:59 2015/03/25 00:14:25 2015/03/25 16:24:29 2015/03/25 01:12:43 Organization AREVA Inc.
AREVA Inc.
AREVA Inc.
AREVA Inc.
AREVA Inc.
AREVA Inc.
Exportkennzeichnung AL: OE001 ECCN: OE001 Die mit "AL ungleich N" gekennzeichneten GOter unterliegen bei der Ausfuhr aus der EU bzw.
innergemeinschaftlichen Verbringung der europaischen bzw. deutschen Ausfuhrgenehmigungspflicht. Die mit "ECCN ungleich N" gekennzeichneten GOter unterliegen 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.
Export classification AL: OE001 ECCN: OE001 Goods labeled with "AL not equal to N" are subject to European or German export authorization when being exported within or out of the EU. Goods labeled with "ECCN not equal to N" are subject to US reexport authorization. Even without a label, or with label "AL: N" or "ECCN: N", authorization may be required due to the final whereabouts and purpose for which the goods are to be used.
CW01L Rev. 4.2-12/12/14
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 2/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA REVISIONS REVISION DATE EXPLANATORY NOTES 1.0 See 1 51 page Initial issue.
release date This is the non-proprietary version of FS 1-0019629.
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology Handling: Restricted AREVA Page 3/18 AREVA Full Name & Title (printed or typed)
Peng WANG Engineer James MOOSE Engineer Scott TYLINSKI, Supervisor Engineer George TOUVANNAS Engineer Documentation of Multiple Analysts, Reviewers, or Approvers (Reference FSOP-7 Appendix 2)
Type of Review Role:
Pages/Sections (applies to W = Writer/Analyst Signature Date Prepared/Reviewed/
Reviewers only}:
R =Reviewer Approved T = Technical A= Approver D = Documentation B =Both w
NIA-Approval of NIA All except Figure 1, document in Figures 5-9 electronic workflow constitutes acceptance.
w NIA-Approval of NIA Figure 1, Figures 5-9 document in electronic workflow constitutes acceptance.
R NIA-Approval of NIA All except Figure 1, B
document in Figures 5-9 electronic workflow constitutes acceptance.
R NIA-Approval of NIA Figure 1, Figures 5-9 B
document in electronic workflow constitutes acceptance.
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 4/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA
- 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 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 9), a realistic fuel channel bow model (Reference 4 ), and expanded coupling with the MICROBURN-B2 core simulator (Reference 5). 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 3 Cycle 19 using the Reference 1 methodology to support extended power uprate (EPU) at Browns Ferry Units 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. [
]
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 5/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA 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 the realistic channel bow model found in Reference 4.
- 3.
ANALYSIS The final core design and step-through, developed by AREVA to meet the operating requirements specified by TVA (Reference 10), was used in the BFE3-19 MCPR safety limit analysis. The BFE3-19 design supports licensed rated power of 3,952 MWt and operation to licensing end of cycle (EOC) cycle exposure of approximately 20,238.3 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 BFE3-19 core is made up of ATRIUM' 10XM* 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 Figure 3 and Figure 4.
The calculated fast fluence gradients for the BFE3-19 core design have been compared to the upper and lower bounds of the channel bow database. As shown in Figure 5, there are [
] 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 same approach as demonstrated in the Response to SNPB RAl-6 in Reference
- 8.
The ACE/ATRIUM 1 OXM critical power correlation (References 3 and 9) is used for the ATRIUM 1 OXM fuel while the SPCB critical power correlation (Reference 6) is used for ATRIUM-10. The fuel-and plant-related uncertainties used in the BFE3-19 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.
[
]
ATRIUM is a trademark of AREVA Inc.
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
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Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 6/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA
[
]
The BFE3-19 SLMCPR analysis supports a TLO SLMCPR of 1.05 and an SLO SLMCPR of 1.06. 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 [
]. The BFE3-19 fuel design is presented in Figures 7 through 9.
- 4.
DISCUSSION OF RESULTS Compared to the TLO and SLO SLMCPR limits at the current licensed thermal power (105% OL TP),
results show a small increase in both the TLO and SLO SLMCPR limits. The SLMCPR differences are a direct result of extended power uprate. To maintain the same design margin, power distributions from the design step-through at EPU power are flatter relative to power distributions at the 105% OL TP thermal power and flatter radial power profile is more likely to produce rods in boiling transition.
- 5.
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 Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.
- 3.
ANP-10298PA Revision 0, ACE/ATRIUM 10XM Critical Power Correlation, AREVA NP, March 2010.
- 4.
BAW-10247PA Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP, February 2008.
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 7/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA
- 5.
EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors:
Evaluation and Validation of CASM0-4 I MICROBURN-82, Siemens Power Corporation, October 1999.
- 6.
EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.
- 7.
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).
- 8.
ANP-3248(P) Revision 1, "AREVA RAI Response for Browns Ferry ATRIUM 10XM Fuel Transition", September 2013.
- 9.
ANP-3140(P) Revision 0, "Browns Ferry Units 1, 2, and 3 Improved K-factor Model for ACE/ATRIUM 10XM Critical Power Correlation," AREVA NP, August 2012.
- 10.
ANP-3372P Revision 0, "Browns Ferry Unit 3 Cycle 19 EPU (120% OL TP) LAR Reference Fuel Cycle Design," AREVA, December 2014.
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Handling: Restricted AREVA
[
Rev. 1.0 Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 8/18 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%
]
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e A
AREVA
No FS 1-0019630 Handling: Restricted AREVA Rev. 1.0 Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 9/18 Limit Analysis With SAFLIM3D Methodology Table 2 Results Summary for MCPR Safety Limit Analysis Percentage of Rods in Boiling SLM CPR Transition TL0-1.05 0.0820 SL0-1.06 0.0978 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type A
AREVA Contribution of Total Rods Predicted to be in BT (%)
Nuclear TLO SLO Fuel Fuel Burn up Type Design Status
[
]
[
]
14 ATRIUM-10 Twice burned
[
16 ATRIUM-10 Twice burned 17 ATRIUM-10 Twice burned 18 ATRIUM-10 Twice burned 19 ATRIUM 10XM Once burned 20 ATRIUM 10XM Once burned 21 ATRIUM 10XM Once burned 22 ATRIUM 10XM Fresh 23 ATRIUM 10XM Fresh 24 ATRIUM 10XM Fresh
]
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology Handling: Restricted AREVA Page 10/18 AREVA 17 16 16 16 17 18 18 18 18 17 16 16 16 16 18 16 19 19 19 19 19 24 24 19 19 19 19 19 16 18 16 16 19 23 23 23 23 19 22 19 19 22 19 23 23 23 23 19 16 16 16 19 23 20 23 20 23 23 23 22 22 23 23 23 20 23 20 23 19 18 17 16 24 19 24 23 24 22 21 22 20 20 22 21 22 24 23 24 19 24 16 17 16 16 16 19 23 23 22 20 22 20 22 21 22 22 21 22 20 22 20 22 23 23 19 16 17 16 16 19 24 23 19 22 20 22 21 22 20 22 21 21 22 20 22 21 22 20 22 19 23 24 19 16 16 19 23 19 23 22 20 22 21 22 20 22 20 22 22 20 22 20 22 21 22 20 22 23 19 23 19 16 18 16 23 20 24 22 20 22 20 22 20 22 20 22 20 20 22 20 22 20 22 20 22 20 22 24 20 23 16 16 16 19 23 23 23 20 22 21 22 21 22 20 22 20 22 22 20 22 20 22 21 22 21 22 20 23 23 23 19 16 16 19 23 20 24 22 21 22 20 22 20 22 21 22 20 20 22 21 22 20 22 20 22 21 22 24 20 23 19 16 16 19 23 23 22 20 22 20 22 20 22 20 22 21 22 22 21 22 20 22 20 22 20 22 20 22 23 23 19 16 16 19 19 23 21 22 20 22 20 22 21 22 20 22 20 20 22 20 22 21 22 20 22 20 22 21 23 19 19 17 18 19 22 23 22 21 22 20 22 20 22 21 22 20 22 22 20 22 21 22 20 22 20 22 21 22 23 22 19 18 18 24 19 22 20 22 21 22 20 22 20 22 20 22 21 21 22 20 22 20 22 20 22 21 22 20 22 19 24 18 18 24 19 22 20 22 21 22 20 22 20 22 20 22 21 21 22 20 22 20 22 20 22 21 22 20 22 19 24 18 18 19 22 23 22 21 22 20 22 20 22 21 22 20 22 22 20 22 21 22 20 22 20 22 21 22 23 22 19 18 16 19 19 23 21 22 20 22 20 22 21 22 20 22 20 20 22 20 22 21 22 20 22 20 22 21 23 19 19 17 16 19 23 23 22 20 22 20 22 20 22 20 22 21 22 22 21 22 20 22 20 22 20 22 20 22 23 23 19 16 16 19 23 20 24 22 21 22 20 22 20 22 21 22 20 20 22 21 22 20 22 20 22 21 22 24 20 23 19 16 16 19 23 23 23 20 22 21 22 21 22 20 22 20 22 22 20 22 20 22 21 22 21 22 20 23 23 23 19 16 17 16 23 20 24 22 20 22 20 22 20 22 20 22 20 20 22 20 22 20 22 20 22 20 22 24 20 23 16 16 17 19 23 19 23 22 20 22 21 22 20 22 20 22 22 20 22 20 22 21 22 20 22 23 19 23 19 17 16 19 24 23 19 22 20 22 21 22 20 22 21 21 22 20 22 21 22 20 22 19 23 24 19 16 16 18 16 19 23 23 22 20 22 20 22 21 22 22 21 22 20 22 20 22 23 23 19 16 18 16 18 16 24 19 24 23 24 22 21 22 20 20 22 21 22 24 23 24 19 24 16 16 18 19 23 20 23 20 23 23 23 22 22 23 23 23 20 23 20 23 19 17 16 16 19 23 23 23 23 19 22 19 19 22 19 23 23 23 23 19 16 18 16 16 19 19 19 19 19 24 24 19 19 19 19 19 16 17 18 16 16 16 16 18 18 18 18 14 16 16 16 17 Nuclear Fuel Cycle Number of Fuel Type Description Loaded Assemblies 14 16 17 18 19 20 21 22 23 24 ATRIUM-10 16 1*
ATRIUM-10 17 67 ATRIUM-10 17 14 ATRIUM-10 17 26 ATRIUM 10XM 18 88 ATRIUM 10XM 18 152 ATRIUM 10XM 18 64 ATRIUM 10XM 19 224 ATRIUM 10XM 19 ATRIUM 10XM 19 Figure 1 Browns Ferry Unit 3 Cycle 19 Core Loading Map 96 32 This fuel assembly is a reinsert that has been withheld from plant operation one cycle for inspection purposes.
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1. 171 1. 385 1.170 1. 338 1. 277 1.161 0. 879 0.592 0. 386 0. 225 0. 892 1. 251 1. 109 1. 347 1. 357 1. 328 1. 268 1. 012 1. 000 0. 591 0. 383 1.169 1. 219 1. 255 1. 267 1. 085 1.209 0. 980 0. 968 0.685 0. 376 0.961 1. 095 0. 992 1. 105 1. 082 1.015 0. 897 0. 655 0.383 0. 230 0. 867 0. 768 0. 756 0. 749 0. 753 0. 689 0. 473 0. 332 0.431 0. 408 0. 398 0. 375 0. 358 0.311 0. 247 Figure 3 Radial Power Distribution Map for Browns Ferry Unit 3 Cycle 19 SLMCPR [
)
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e A
AREVA
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 13/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA 200 175 150 CJ)
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]
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 14/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA Figure 5 Channel Fluence Gradient Distribution for Browns Ferry Unit 3 Cycle 19 AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 15/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA Figure 6 Browns Ferry Unit 3 Cycle 19 Reference Full Core Loading Pattern AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
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Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 16/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA Figure 7 [
]
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
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Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 17/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA Figure 8 [
]
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 18/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA Figure 9 [
]
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
ATTACHMENT 33 FS1-0019630, Browns Ferry Unit 3 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology (Non-Proprietary)
IDENTIFICATION REVISION I
FS1-0019630 11 1.0 I
AREVA Front End BG A
Fuel BU AREVA TOTAL NUMBER OF PAGES: 18 Browns Ferry Unit 3 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology ADDITIONAL INFORMATION:
BFE3 Cycle 19 PROJECT DISTRIBUTION TO PURPOSE OF DISTRIBUTION HANDLING Restricted AREVA CATEGORY EIR - Engineering Information Report 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: 09012167806b9cb0 Role Name Writer WANG Peng Writer MOOSE James Reviewer TYLINSKI Scott Reviewer TOUVANNAS George Approver MEGINNIS Alan Approver SCHNEPP Robert RELEASE DATA:
SAFETY RELATED DOCUMENT:
y CHANGE CONTROL RECORDS:
France:
N This document, when revised, must be USA:
y reviewed or approved by the following regions:
Germany:
N
- Release date (YYYY/MM/DD) : 2015/03/25 16:24:36
[Western European Time]
Date (YYYY/MM/DD) 2015/03/25 00:00:23 2015/03/24 23:43:23 2015/03/25 00:27:59 2015/03/25 00:14:25 2015/03/25 16:24:29 2015/03/25 01:12:43 Organization AREVA Inc.
AREVA Inc.
AREVA Inc.
AREVA Inc.
AREVA Inc.
AREVA Inc.
Exportkennzeichnung AL: OE001 ECCN: OE001 Die mit "AL ungleich N" gekennzeichneten GOter unterliegen bei der Ausfuhr aus der EU bzw.
innergemeinschaftlichen Verbringung der europaischen bzw. deutschen Ausfuhrgenehmigungspflicht. Die mit "ECCN ungleich N" gekennzeichneten GOter unterliegen 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.
Export classification AL: OE001 ECCN: OE001 Goods labeled with "AL not equal to N" are subject to European or German export authorization when being exported within or out of the EU. Goods labeled with "ECCN not equal to N" are subject to US reexport authorization. Even without a label, or with label "AL: N" or "ECCN: N", authorization may be required due to the final whereabouts and purpose for which the goods are to be used.
CW01L Rev. 4.2-12/12/14
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 2/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA REVISIONS REVISION DATE EXPLANATORY NOTES 1.0 See 1 51 page Initial issue.
release date This is the non-proprietary version of FS 1-0019629.
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology Handling: Restricted AREVA Page 3/18 AREVA Full Name & Title (printed or typed)
Peng WANG Engineer James MOOSE Engineer Scott TYLINSKI, Supervisor Engineer George TOUVANNAS Engineer Documentation of Multiple Analysts, Reviewers, or Approvers (Reference FSOP-7 Appendix 2)
Type of Review Role:
Pages/Sections (applies to W = Writer/Analyst Signature Date Prepared/Reviewed/
Reviewers only}:
R =Reviewer Approved T = Technical A= Approver D = Documentation B =Both w
NIA-Approval of NIA All except Figure 1, document in Figures 5-9 electronic workflow constitutes acceptance.
w NIA-Approval of NIA Figure 1, Figures 5-9 document in electronic workflow constitutes acceptance.
R NIA-Approval of NIA All except Figure 1, B
document in Figures 5-9 electronic workflow constitutes acceptance.
R NIA-Approval of NIA Figure 1, Figures 5-9 B
document in electronic workflow constitutes acceptance.
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 4/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA
- 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 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 9), a realistic fuel channel bow model (Reference 4 ), and expanded coupling with the MICROBURN-B2 core simulator (Reference 5). 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 3 Cycle 19 using the Reference 1 methodology to support extended power uprate (EPU) at Browns Ferry Units 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. [
]
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 5/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA 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 the realistic channel bow model found in Reference 4.
- 3.
ANALYSIS The final core design and step-through, developed by AREVA to meet the operating requirements specified by TVA (Reference 10), was used in the BFE3-19 MCPR safety limit analysis. The BFE3-19 design supports licensed rated power of 3,952 MWt and operation to licensing end of cycle (EOC) cycle exposure of approximately 20,238.3 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 BFE3-19 core is made up of ATRIUM' 10XM* 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 Figure 3 and Figure 4.
The calculated fast fluence gradients for the BFE3-19 core design have been compared to the upper and lower bounds of the channel bow database. As shown in Figure 5, there are [
] 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 same approach as demonstrated in the Response to SNPB RAl-6 in Reference
- 8.
The ACE/ATRIUM 1 OXM critical power correlation (References 3 and 9) is used for the ATRIUM 1 OXM fuel while the SPCB critical power correlation (Reference 6) is used for ATRIUM-10. The fuel-and plant-related uncertainties used in the BFE3-19 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.
[
]
ATRIUM is a trademark of AREVA Inc.
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
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[
]
The BFE3-19 SLMCPR analysis supports a TLO SLMCPR of 1.05 and an SLO SLMCPR of 1.06. 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 [
]. The BFE3-19 fuel design is presented in Figures 7 through 9.
- 4.
DISCUSSION OF RESULTS Compared to the TLO and SLO SLMCPR limits at the current licensed thermal power (105% OL TP),
results show a small increase in both the TLO and SLO SLMCPR limits. The SLMCPR differences are a direct result of extended power uprate. To maintain the same design margin, power distributions from the design step-through at EPU power are flatter relative to power distributions at the 105% OL TP thermal power and flatter radial power profile is more likely to produce rods in boiling transition.
- 5.
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 Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.
- 3.
ANP-10298PA Revision 0, ACE/ATRIUM 10XM Critical Power Correlation, AREVA NP, March 2010.
- 4.
BAW-10247PA Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP, February 2008.
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 7/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA
- 5.
EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors:
Evaluation and Validation of CASM0-4 I MICROBURN-82, Siemens Power Corporation, October 1999.
- 6.
EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.
- 7.
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).
- 8.
ANP-3248(P) Revision 1, "AREVA RAI Response for Browns Ferry ATRIUM 10XM Fuel Transition", September 2013.
- 9.
ANP-3140(P) Revision 0, "Browns Ferry Units 1, 2, and 3 Improved K-factor Model for ACE/ATRIUM 10XM Critical Power Correlation," AREVA NP, August 2012.
- 10.
ANP-3372P Revision 0, "Browns Ferry Unit 3 Cycle 19 EPU (120% OL TP) LAR Reference Fuel Cycle Design," AREVA, December 2014.
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Handling: Restricted AREVA
[
Rev. 1.0 Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 8/18 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%
]
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e A
AREVA
No FS 1-0019630 Handling: Restricted AREVA Rev. 1.0 Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 9/18 Limit Analysis With SAFLIM3D Methodology Table 2 Results Summary for MCPR Safety Limit Analysis Percentage of Rods in Boiling SLM CPR Transition TL0-1.05 0.0820 SL0-1.06 0.0978 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type A
AREVA Contribution of Total Rods Predicted to be in BT (%)
Nuclear TLO SLO Fuel Fuel Burn up Type Design Status
[
]
[
]
14 ATRIUM-10 Twice burned
[
16 ATRIUM-10 Twice burned 17 ATRIUM-10 Twice burned 18 ATRIUM-10 Twice burned 19 ATRIUM 10XM Once burned 20 ATRIUM 10XM Once burned 21 ATRIUM 10XM Once burned 22 ATRIUM 10XM Fresh 23 ATRIUM 10XM Fresh 24 ATRIUM 10XM Fresh
]
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Limit Analysis With SAFLIM3D Methodology Handling: Restricted AREVA Page 10/18 AREVA 17 16 16 16 17 18 18 18 18 17 16 16 16 16 18 16 19 19 19 19 19 24 24 19 19 19 19 19 16 18 16 16 19 23 23 23 23 19 22 19 19 22 19 23 23 23 23 19 16 16 16 19 23 20 23 20 23 23 23 22 22 23 23 23 20 23 20 23 19 18 17 16 24 19 24 23 24 22 21 22 20 20 22 21 22 24 23 24 19 24 16 17 16 16 16 19 23 23 22 20 22 20 22 21 22 22 21 22 20 22 20 22 23 23 19 16 17 16 16 19 24 23 19 22 20 22 21 22 20 22 21 21 22 20 22 21 22 20 22 19 23 24 19 16 16 19 23 19 23 22 20 22 21 22 20 22 20 22 22 20 22 20 22 21 22 20 22 23 19 23 19 16 18 16 23 20 24 22 20 22 20 22 20 22 20 22 20 20 22 20 22 20 22 20 22 20 22 24 20 23 16 16 16 19 23 23 23 20 22 21 22 21 22 20 22 20 22 22 20 22 20 22 21 22 21 22 20 23 23 23 19 16 16 19 23 20 24 22 21 22 20 22 20 22 21 22 20 20 22 21 22 20 22 20 22 21 22 24 20 23 19 16 16 19 23 23 22 20 22 20 22 20 22 20 22 21 22 22 21 22 20 22 20 22 20 22 20 22 23 23 19 16 16 19 19 23 21 22 20 22 20 22 21 22 20 22 20 20 22 20 22 21 22 20 22 20 22 21 23 19 19 17 18 19 22 23 22 21 22 20 22 20 22 21 22 20 22 22 20 22 21 22 20 22 20 22 21 22 23 22 19 18 18 24 19 22 20 22 21 22 20 22 20 22 20 22 21 21 22 20 22 20 22 20 22 21 22 20 22 19 24 18 18 24 19 22 20 22 21 22 20 22 20 22 20 22 21 21 22 20 22 20 22 20 22 21 22 20 22 19 24 18 18 19 22 23 22 21 22 20 22 20 22 21 22 20 22 22 20 22 21 22 20 22 20 22 21 22 23 22 19 18 16 19 19 23 21 22 20 22 20 22 21 22 20 22 20 20 22 20 22 21 22 20 22 20 22 21 23 19 19 17 16 19 23 23 22 20 22 20 22 20 22 20 22 21 22 22 21 22 20 22 20 22 20 22 20 22 23 23 19 16 16 19 23 20 24 22 21 22 20 22 20 22 21 22 20 20 22 21 22 20 22 20 22 21 22 24 20 23 19 16 16 19 23 23 23 20 22 21 22 21 22 20 22 20 22 22 20 22 20 22 21 22 21 22 20 23 23 23 19 16 17 16 23 20 24 22 20 22 20 22 20 22 20 22 20 20 22 20 22 20 22 20 22 20 22 24 20 23 16 16 17 19 23 19 23 22 20 22 21 22 20 22 20 22 22 20 22 20 22 21 22 20 22 23 19 23 19 17 16 19 24 23 19 22 20 22 21 22 20 22 21 21 22 20 22 21 22 20 22 19 23 24 19 16 16 18 16 19 23 23 22 20 22 20 22 21 22 22 21 22 20 22 20 22 23 23 19 16 18 16 18 16 24 19 24 23 24 22 21 22 20 20 22 21 22 24 23 24 19 24 16 16 18 19 23 20 23 20 23 23 23 22 22 23 23 23 20 23 20 23 19 17 16 16 19 23 23 23 23 19 22 19 19 22 19 23 23 23 23 19 16 18 16 16 19 19 19 19 19 24 24 19 19 19 19 19 16 17 18 16 16 16 16 18 18 18 18 14 16 16 16 17 Nuclear Fuel Cycle Number of Fuel Type Description Loaded Assemblies 14 16 17 18 19 20 21 22 23 24 ATRIUM-10 16 1*
ATRIUM-10 17 67 ATRIUM-10 17 14 ATRIUM-10 17 26 ATRIUM 10XM 18 88 ATRIUM 10XM 18 152 ATRIUM 10XM 18 64 ATRIUM 10XM 19 224 ATRIUM 10XM 19 ATRIUM 10XM 19 Figure 1 Browns Ferry Unit 3 Cycle 19 Core Loading Map 96 32 This fuel assembly is a reinsert that has been withheld from plant operation one cycle for inspection purposes.
AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
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0. 689 0. 383 0. 897 1. 256 1. 114 1. 352 1. 361 1. 332 1. 272 1. 017 1. 003 0. 593 0. 375 1.056 1. 087 1. 348 1. 176 1. 390 1.174 1. 342 1. 281 1.165 0. 881 0.595 0. 377 0. 222 1. 106 1. 339 1. 173 1. 373 1. 164 1. 379 1. 181 1. 340 1. 128 1. 166 1. 005 0. 693 0. 384 1. 363 1. 179 1. 350 1. 144 1. 329 1. 147 1. 375 1. 184 1. 343 1. 284 1. 021 0. 973 0. 659 0. 332 1.189 1. 360 1. 127 1. 090 0. 960 1.318 1. 176 1. 383 1.193 1. 346 1.275 0. 986 0. 902 0.478 0. 257 1. 347 1. 139 1. 283 0. 940 1. 073 1. 085 1. 356 1. 174 1. 386 1. 174 1. 334 1. 217 1. 023 0. 696 0. 317 1. 112 1. 280 1. 060 1. 227 1. 070 1. 291 1. 138 1. 356 1. 155 1. 381 1. 364 1. 093 1. 093 0. 762 0. 360 1.158 1. 006 1. 194 1. 004 1. 195 1.090 1. 282 1. 108 1.303 1. 148 1.348 1. 281 1. 122 0.761 0. 381 0.706 1. 084 0. 953 0. 886 0. 781 1.185 1. 048 1. 044 0.914 1. 284 1.117 1. 283 1. 020 0.773 0. 394 0. 759 0. 900 1. 059 0. 736 0. 883 0. 991 1. 191 0. 885 1. 039 1. 074 1. 307 1. 277 1. 140 0. 798 0. 422 0.842 1. 037 0. 931 1. 062 0. 957 1.166 1. 026 1. 199 1.031 1. 271 1.116 1. 265 1. 010 0.906 0. 452 0.842 1. 036 0. 929 1. 062 0. 957 1.166 1. 026 1. 199 1.031 1. 270 1.115 1. 265 1. 009 0.905 0. 450 0. 758 0. 899 1. 058 0. 735 0. 882 0. 990 1. 190 0. 885 1. 038 1. 073 1. 306 1. 276 1. 138 0. 794 0. 422 0.704 1. 082 0. 950 0. 885 0. 779 1.184 1. 047 1. 044 0.914 1. 284 1.115 1. 282 1. 014 0.771 0. 393 1.155 1. 003 1. 191 1. 002 1. 192 1.086 1. 283 1. 108 1.302 1. 147 1.347 1. 279 1. 120 0.759 0. 380 1. 110 1. 276 1. 056 1. 223 1. 067 1. 289 1. 149 1. 356 1. 153 1. 380 1. 363 1. 091 1. 091 0. 760 0. 359 1.343 1. 136 1. 278 0. 934 1. 068 1.082 1. 355 1. 171 1.384 1. 173 1.333 1. 216 1. 021 0.695 0. 315 1.186 1. 355 1. 122 1. 084 0. 942 1.313 1. 172 1. 381 1.191 1. 345 1.274 0. 984 0. 901 0.477 0. 251 1. 359 1. 175 1. 344 1. 138 1. 322 1. 141 1. 371 1. 182 1. 340 1. 282 1. 018 0. 972 0. 658 0. 333 1.102 1. 333 1. 167 1. 367 1. 159 1.374 1. 178 1. 337 1.122 1. 164 1.003 0. 690 0. 384 1.051 1. 082 1. 342 1. 171 1. 385 1.170 1. 338 1. 277 1.161 0. 879 0.592 0. 386 0. 225 0. 892 1. 251 1. 109 1. 347 1. 357 1. 328 1. 268 1. 012 1. 000 0. 591 0. 383 1.169 1. 219 1. 255 1. 267 1. 085 1.209 0. 980 0. 968 0.685 0. 376 0.961 1. 095 0. 992 1. 105 1. 082 1.015 0. 897 0. 655 0.383 0. 230 0. 867 0. 768 0. 756 0. 749 0. 753 0. 689 0. 473 0. 332 0.431 0. 408 0. 398 0. 375 0. 358 0.311 0. 247 Figure 3 Radial Power Distribution Map for Browns Ferry Unit 3 Cycle 19 SLMCPR [
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AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e A
AREVA
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 13/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA 200 175 150 CJ)
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AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 14/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA Figure 5 Channel Fluence Gradient Distribution for Browns Ferry Unit 3 Cycle 19 AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 15/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA Figure 6 Browns Ferry Unit 3 Cycle 19 Reference Full Core Loading Pattern AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 16/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA Figure 7 [
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AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 17/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA Figure 8 [
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AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e
No FS 1-0019630 Rev. 1.0 A
Browns Ferry Unit 3 Cycle 19 MCPR Safety Page 18/18 Limit Analysis With SAFLIM3D Methodology AREVA Handling: Restricted AREVA Figure 9 [
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AREVA-Fuel BU This document is sub"ect to the restrictions set forth on the first or title a e