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| =Text= | | =Text= |
| {{#Wiki_filter:John A. Krakuszeski Vice President Brunswick Nuclear Plant 8470 River Rd SE Southport, NC 28461 Enclosures 1, 3, 5, and 7 Contain Proprietary Information o: 910.832.3698 Withhold in Accordance with 10 CFR 2.390 October 23, 2019 Serial: RA-19-0411 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 | | {{#Wiki_filter:}} |
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| ==Subject:==
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| Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies
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| ==Reference:==
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| : 1. Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, dated October 11, 2018, ADAMS Accession Number ML18284A395.
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| : 2. Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, dated March 18, 2019, ADAMS Accession Number ML19077A293.
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| Ladies and Gentlemen:
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| By letter dated October 11, 2018 (i.e., Reference 1), Duke Energy Progress, LLC (Duke Energy), submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed license amendment revises Technical Specification 5.6.5.b to allow application of Advanced Framatome Methodologies for determining core operating limits in support of loading Framatome fuel type ATRIUM 11.
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| As committed to in the subject LAR, the BSEP Unit 1 Cycle 23 Reload Safety Analysis Report (i.e., ANP-3808P) and the BSEP Unit 1 Cycle 23 ATRIUM 11 Fuel Rod Design Report (i.e., ANP-3791P) are being transmitted to the NRC for information. These reports are included in Enclosures 1 and 3 respectively.
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| In addition, the BSEP Unit 1 Cycle 23 Fuel Cycle Design Report (i.e., ANP-3759P) and the BSEP Unit 1 Cycle 23 Nuclear Fuel Bundle Design Report (i.e., ANP-3758P), which were transmitted to the NRC for information under Reference 2, have been revised and are included in Enclosures 5 and 7, respectively.
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| U.S. Nuclear Regulatory Commission Page 2 of 3 Enclosures 1, 3, 5, and 7 contain information considered proprietary to Framatome. The proprietary information in these reports has been denoted by brackets. As owner of the proprietary information, Framatome has executed the affidavits contained in Enclosure 9 which identifies the information as proprietary, is customarily held in confidence, and should be withheld from public disclosure in accordance with 10 CFR 2.390. Enclosures 2, 4, 6, and 8 provide the non-proprietary versions of these reports.
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| Please refer any questions regarding this submittal to Ms. Sabrina Salazar, Manager - Nuclear Support Services, at (910) 832-3207.
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| I declare, under penalty of perjury, that the foregoing is true and correct. Executed on October 23, 2019.
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| Sincerely, John A. Krakuszeski SBY/sby
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| ==Enclosures:==
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| : 1. ANP-3808P, Brunswick Unit 1 Cycle 23 Reload Safety Analysis, Revision O
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| [Proprietary Information - Withhold from Public Disclosure in Accordance with 10 CFR 2.390]
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| : 2. ANP-3808NP, Brunswick Unit 1 Cycle 23 Reload Safety Analysis, Revision O
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| : 3. ANP-3791 P, A TR/UM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23, Revision O [Proprietary Information - Withhold from Public Disclosure in Accordance with 10 CFR 2.390]
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| : 4. ANP-3791 NP, ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23, Revision O
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| : 5. ANP-3759P, Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report, Revision 2
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| [Proprietary Information - Withhold from Public Disclosure in Accordance with 10 CFR 2.390]
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| : 6. ANP-3759NP, Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report, Revision 2
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| : 7. ANP-3758P, Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report, Revision 1 [Proprietary Information -Withhold from Public Disclosure in Accordance with 10 CFR 2.390]
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| : 8. ANP-3758NP, Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report, Revision 1
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| : 9. Affidavits for ANP-3808P, ANP-3791P, ANP-3759P, and ANP-3758P
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| U.S. Nuclear Regulatory Commission Page 3 of 3 cc (with all Enclosures):
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| U. S. Nuclear Regulatory Commission, Region II ATTN: Ms. Laura Dudes, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Gale Smith, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon 11555 Rockville Pike Rockville, MD 20852-2738 cc (with Enclosures 2, 4, 6, 8, and 9 only):
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| Chair - North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net Mr. W. Lee Cox, III, Section Chief (Electronic Copy Only)
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| Radiation Protection Section North Carolina Department of Health and Human Services 1645 Mail Service Center Raleigh, NC 27699-1645 lee.cox@dhhs.nc.gov
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| RA-19-0411 Enclosure 2 ANP-3808NP, Brunswick Unit 1 Cycle 23 Reload Safety Analysis, Revision 0
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| Controlled Document 0414-12-F04 (Rev. 003, 09/17/2018)
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| Brunswick Unit 1 Cycle 23 ANP-3808NP Revision 0 Reload Safety Analysis October 2019
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| © 2019 Framatome Inc.
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| Controlled Document ANP-3808NP Revision 0 Copyright © 2019 Framatome Inc.
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| All Rights Reserved ATRIUM is a trademark or registered trademark of Framatome or its affiliates, in the USA or other countries.
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| Framatome Inc Controlled Document ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page i Nature of Changes Section(s)
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| Item or Page(s) Description and Justification 1 All Initial Issue
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| Framatome Inc Controlled Document ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page ii Contents
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| ==1.0 INTRODUCTION==
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| .................................................................................................. 1 2.0 DISPOSITION OF EVENTS AND PLANT MODELING SENSITIVITIES .................................................................................................... 4 2.1 Disposition of Events for ATRIUM 11 Fuel Introduction ............................. 4 2.2 Plant Specific Modeling Sensitivities ........................................................ 12 3.0 MECHANICAL DESIGN ANALYSIS ................................................................... 26 4.0 THERMAL-HYDRAULIC DESIGN ANALYSIS ................................................... 27 4.1 Thermal-Hydraulic Design and Compatibility ........................................... 27 4.2 Safety Limit MCPR Analysis .................................................................... 27 4.3 Core Hydrodynamic Stability.................................................................... 28 4.4 Voiding in the Channel Bypass Region .................................................... 29 5.0 ANTICIPATED OPERATIONAL OCCURRENCES ............................................ 36 5.1 System Transients ................................................................................... 37 5.1.1 Load Rejection No Bypass (LRNB) ............................................... 39 5.1.2 Turbine Trip No Bypass (TTNB) .................................................... 39 5.1.3 Feedwater Controller Failure (FWCF) ........................................... 40 5.1.4 Pressure Regulator Failure Downscale (PRFDS) ......................... 41 5.1.5 Loss of Feedwater Heating ........................................................... 41 5.1.6 Control Rod Withdrawal Error ....................................................... 42 5.2 Slow Flow Runup Analysis ....................................................................... 42 5.3 Equipment Out-of-Service Scenarios ....................................................... 43 5.3.1 FHOOS ......................................................................................... 43 5.3.2 TBVOOS ....................................................................................... 44 5.3.3 Combined FHOOS and TBVOOS ................................................. 44 5.3.4 One SRVOOS ............................................................................... 44 5.3.5 One MSIVOOS.............................................................................. 44 5.3.6 Single-Loop Operation .................................................................. 45 5.4 Licensing Power Shape ........................................................................... 45 6.0 POSTULATED ACCIDENTS .............................................................................. 67 6.1 Loss-of-Coolant Accident (LOCA) ............................................................ 67 6.2 Control Rod Drop Accident (CRDA) ......................................................... 67 6.3 Fuel and Equipment Handling Accident ................................................... 68 6.4 Fuel Loading Error (Infrequent Event) ..................................................... 69 6.4.1 Mislocated Fuel Bundle............................................................................ 69
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| Framatome Inc Controlled Document ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page iii 6.4.2 Misoriented Fuel Bundle .......................................................................... 69 7.0 SPECIAL ANALYSES ........................................................................................ 70 7.1 ASME Overpressurization Analysis ......................................................... 70 7.2 ATWS Event Evaluation........................................................................... 71 7.2.1 ATWS Overpressurization Analysis .............................................. 71 7.2.2 Long-Term Evaluation ................................................................... 72 7.2.3 ATWS with Core Instability ............................................................ 73 7.3 Standby Liquid Control System................................................................ 73 7.4 Fuel Criticality .......................................................................................... 73 7.5 Strongest Rod Out Shutdown Margin ...................................................... 73 8.0 OPERATING LIMITS AND COLR INPUT ........................................................... 85 8.1 MCPR Limits ............................................................................................ 85 8.2 LHGR Limits ............................................................................................ 86 8.3 MAPLHGR Limits ..................................................................................... 87
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| ==9.0 REFERENCES==
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| ................................................................................................. 108
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| Framatome Inc Controlled Document ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page iv Tables Table 1.1 EOOS Operating Conditions ...................................................................... 2 Table 2.1 Disposition of Events Summary for ATRIUM 11 Fuel Introduction at Brunswick .................................................................................................. 6 Table 2.2 Disposition of Operating Flexibility and EOOS Options on Limiting Events ...................................................................................................... 10 Table 2.3 Plant Parameter Sensitivity Results for MCPR ...................................... 15 Table 2.4 Plant Parameter Sensitivity Results for Transient Nodal Power .............. 19 Table 2.5 Plant Parameter Sensitivity Results for Overpressurization .................... 23 Table 4.1 Fuel- and Plant-Related Uncertainties for Safety Limit MCPR Analyses .................................................................................................. 30 Table 4.2 Results Summary for Safety Limit MCPR Analyses ................................. 31 Table 4.3 BSP Endpoints For Nominal Feedwater Temperature ............................. 32 Table 4.4 BSP Endpoints For Reduced Feedwater Temperature ............................ 33 Table 4.5 ABSP Setpoints for the Scram Region..................................................... 34 Table 4.6 Maximum Bypass Voiding at LPRM Level D............................................ 35 Table 5.1 Exposure Basis for Brunswick Unit 1 Cycle 23 Transient Analysis .......... 47 Table 5.2 Scram Speed Insertion Times.................................................................. 48 Table 5.3 EOCLB Base Case Limiting Transient Event NSS Insertion Time ........... 49 Table 5.4 EOCLB Base Case Limiting Transient Event ESS Insertion Time ........... 50 Table 5.5 EOCLB Base Case Limiting Transient Event TSSS Insertion Time ......... 51 Table 5.6 Loss of Feedwater Heating Transient Analysis Results ........................... 52 Table 5.7 Control Rod Withdrawal Error CPR Results .......................................... 52 Table 5.8 RBM Operability Requirements ............................................................... 53 Table 5.9 Flow-Dependent MCPR Results .............................................................. 53 Table 5.10 EOCLB LHGRFACp Transient Results NSS Insertion Time ................... 54 Table 5.11 EOCLB LHGRFACp Transient Results ESS Insertion Time ................... 55 Table 5.12 EOCLB LHGRFACp Transient Results TSSS Insertion Time ................. 56 Table 5.13 Licensing Basis Core Average Axial Power Profile .................................. 57 Table 7.1 ASME Overpressurization Analysis Results ........................................... 74 Table 7.2 ATWS Overpressurization Analysis Results ........................................... 75
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| Framatome Inc Controlled Document ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page v Table 7.3 [
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| ] ............................................................................................. 76 Table 8.1 MCPRp Limits for NSS Insertion Times BOC to < NEOC......................... 88 Table 8.2 MCPRp Limits for ESS Insertion Times BOC to < NEOC ......................... 89 Table 8.3 MCPRp Limits for TSSS Insertion Times BOC to < NEOC....................... 90 Table 8.4 MCPRp Limits for NSS Insertion Times BOC to < EOCLB ....................... 91 Table 8.5 MCPRp Limits for ESS Insertion Times BOC to < EOCLB ....................... 92 Table 8.6 MCPRp Limits for TSSS Insertion Times BOC to < EOCLB ..................... 93 Table 8.7 MCPRp Limits for NSS Insertion Times FFTR/Coastdown ...................... 94 Table 8.8 MCPRp Limits for ESS Insertion Times FFTR/Coastdown ...................... 95 Table 8.9 MCPRp Limits for TSSS Insertion Times FFTR/Coastdown .................... 96 Table 8.10 Flow-Dependent MCPR Limits ATRIUM 10XM Fuel ................................ 97 Table 8.11 Flow-Dependent MCPR Limits ATRIUM 11 Fuel ..................................... 97 Table 8.12 Steady-State LHGR Limits ....................................................................... 98 Table 8.13 LHGRFACp Multipliers for NSS Insertion Times BOC to < EOCLB ......... 99 Table 8.14 LHGRFACp Multipliers for ESS Insertion Times BOC to < EOCLB........ 100 Table 8.15 LHGRFACp Multipliers for TSSS Insertion Times BOC to < EOCLB ..... 101 Table 8.16 LHGRFACp Multipliers for NSS Insertion Times FFTR/Coastdown ....... 102 Table 8.17 LHGRFACp Multipliers for ESS Insertion Times FFTR/Coastdown........ 103 Table 8.18 LHGRFACp Multipliers for TSSS Insertion Times FFTR/Coastdown ..... 104 Table 8.19 ATRIUM 10XM and ATRIUM 11 LHGRFACf Multipliers All Cycle 23 Exposures .............................................................................................. 105 Table 8.20 Framatome Fuel MAPLHGR Limits ....................................................... 105 Figures Figure 1.1 Brunswick Unit 1 Power/Flow Map ............................................................ 3 Figure 5.1 EOCLB LRNB at 100P/104.5F - TSSS Key Parameters ......................... 58 Figure 5.2 EOCLB LRNB at 100P/104.5F - TSSS Sensed Water Level .................. 59 Figure 5.3 EOCLB LRNB at 100P/104.5F - TSSS Vessel Pressures....................... 60 Figure 5.4 EOCLB TTNB at 100P/104.5F - TSSS Key Parameters ......................... 61 Figure 5.5 EOCLB TTNB at 100P/104.5F - TSSS Sensed Water Level .................. 62
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| Framatome Inc Controlled Document ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page vi Figure 5.6 EOCLB TTNB at 100P/104.5F - TSSS Vessel Pressures ....................... 63 Figure 5.7 EOCLB FWCF at 100P/104.5F - TSSS Key Parameters ........................ 64 Figure 5.8 EOCLB FWCF at 100P/104.5F - TSSS Sensed Water Level ................. 65 Figure 5.9 EOCLB FWCF at 100P/104.5F - TSSS Vessel Pressures ...................... 66 Figure 7.1 MSIV Closure Overpressurization Event at 102P/104.5F - Key Parameters .............................................................................................. 77 Figure 7.2 MSIV Closure Overpressurization Event at 102P/104.5F - Sensed Water Level.............................................................................................. 78 Figure 7.3 MSIV Closure Overpressurization Event at 102P/104.5F - Vessel Pressures................................................................................................. 79 Figure 7.4 MSIV Closure Overpressurization Event at 102P/104.5F -
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| Safety/Relief Valve Flow Rates................................................................ 80 Figure 7.5 MSIV ATWS Overpressurization Event at 100P/85F - Key Parameters .............................................................................................. 81 Figure 7.6 MSIV ATWS Overpressurization Event at 100P/85F - Sensed Water Level.............................................................................................. 82 Figure 7.7 MSIV ATWS Overpressurization Event at 100P/85F - Vessel Pressures................................................................................................. 83 Figure 7.8 MSIV ATWS Overpressurization Event at 100P/85F - Safety/Relief Valve Flow Rates ..................................................................................... 84 Figure 8.1 [
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| ] .............................................. 106 Figure 8.2 [
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| ] ............................................................. 107
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| Framatome Inc Controlled Document ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page vii Nomenclature ABSP automated backup stability protection APRM average power range monitor AOO anticipated operational occurrence ARO all control rods out ASME American Society of Mechanical Engineers AST alternative source term ATWS anticipated transient without scram ATWS-I anticipated transient without scram with instability ATWS-RPT anticipated transient without scram recirculation pump trip BEO-III best estimate enhanced option III BOC beginning-of-cycle BPWS banked position withdrawal sequence BSP backup stability protection BWROG Boiling Water Reactor Owners Group CDA confirmation density algorithm CFR Code of Federal Regulations COLR core operating limits report CPR critical power ratio CRDA control rod drop accident CRWE control rod withdrawal error EFPD effective full-power days EFPH effective full-power hours EOC end-of-cycle EOCLB end-of-cycle licensing basis EOFP end of full power EOOS equipment out-of-service FFTR final feedwater temperature reduction FHA fuel handling accident FHOOS feedwater heaters out-of-service FWCF feedwater controller failure GE General Electric GSF generic shape function HCOM hot channel oscillation magnitude HFCL high flow control line ICF increased core flow LFWH loss of feedwater heating LHGR linear heat generation rate LHGRFACf flow-dependent linear heat generation rate multipliers LHGRFACp power-dependent linear heat generation rate multipliers LOCA loss-of-coolant accident LPRM local power range monitor LRNB generator load rejection with no bypass
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| Framatome Inc Controlled Document ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page viii Nomenclature (Continued)
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| MAPLHGR maximum average planar linear heat generation rate MCPR minimum critical power ratio MCPRf flow-dependent minimum critical power ratio MCPRp power-dependent minimum critical power ratio MELLLA maximum extended load line limit analysis MELLLA+ maximum extended load line limit analysis plus MSIV main steam isolation valve MSIVIS main steam isolation valve in-service MSIVOOS main steam isolation valve out-of-service NCL natural circulation line NEOC near end-of-cycle NSS nominal scram speed NRC Nuclear Regulatory Commission, U.S.
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| OLMCPR operating limit minimum critical power ratio OOS out-of-service OPRM oscillation power range monitor Pbypass power below which direct scram on TSV/TCV closure is bypassed PCT peak cladding temperature PLU power load unbalance PRFDS pressure regulator failure downscale PRFO pressure regulator failure open PROOS pressure regulator out-of-service RBM (control) rod block monitor RDF recirculation drive flow RHR residual heat removal RPS reactor protection system RPT recirculation pump trip RTP rated thermal power SAD amplitude discriminator setpoint SLC standby liquid control SLMCPR safety limit minimum critical power ratio SLO single-loop operation SRV safety/relief valve SRVOOS safety/relief valve out-of-service SS steady state STP simulated thermal power TBVOOS turbine bypass valves out-of-service TCV turbine control valve TIP traversing incore probe TLO two-loop operation TSSS technical specifications scram speed TSV turbine stop valve TTNB turbine trip with no bypass CPR change in critical power ratio 2PT 2 pump trip
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 1
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| ==1.0 INTRODUCTION==
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| Reload licensing analyses results generated by Framatome Inc. are presented in support of Brunswick Unit 1 Cycle 23. The analyses reported in this document, with the exception of the ATWS-I and stability methodologies, were performed using methodologies previously approved for generic application to boiling water reactors and demonstrated in Reference 1 to be applicable for ATRIUM 11 fuel operating in the MELLLA+ extended flow operating domain, Reference 2. The NRC technical limitations associated with the application of the approved methodologies have been satisfied by these analyses. The ATWS-I and stability methodologies were applied on a plant specific basis which are currently under NRC review in Reference 8.
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| The Cycle 23 core consists of a total of 560 fuel assemblies, including 226 fresh ATRIUM 11 assemblies, and 334 irradiated ATRIUM 10XM assemblies. The licensing analysis supports the core design presented in Reference 3 and the use of the MELLLA+ operating domain.
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| The Cycle 23 reload licensing analyses were performed for the potentially limiting events and analyses that were identified in the disposition of events. The results of the analyses are used to establish the Technical Specifications/COLR limits and ensure that the design and licensing criteria are met. The design and safety analyses are based on the design and operational assumptions and plant parameters provided by the utility. The results of the reload licensing analysis support operation for the power/flow map presented in Figure 1.1. This reload licensing also supports operation with the equipment out-of-service (EOOS) scenarios presented in Table 1.1.
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| The results in this report comply with the license condition related to the range of applicability for the channel bow model. This license condition was added with the inclusion of the SAFLIM3D methodology to the list of approved references in Section 5.6.5(b) of the Brunswick Technical Specifications.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 2 Table 1.1 EOOS Operating Conditions*
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| Single-loop operation (SLO),
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| Turbine bypass valves out-of-service (TBVOOS)
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| Feedwater heaters out-of-service (FHOOS)
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| One safety relief valve out-of-service (SRVOOS)
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| One main steam isolation valve out-of-service§ (MSIVOOS)
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| One pressure regulator out-of-service**
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| Up to 40% of the TIP channels out-of-service (100%
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| available at startup)
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| Up to 50% of the LPRMs out-of-service
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| * Each EOOS condition is supported in combination with 1 SRVOOS, up to 40% of the TIP channels out-of-service, and/or up to 50% of the LPRMs out-of-service.
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| Note that single-loop operation, and feedwater heaters out-of-service conditions are not allowed when operating in the MELLLA+ domain.
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| Operation in SLO is only supported up to a maximum power level of 71.1% of rated.
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| § Operation with one MSIVOOS is only supported at power levels less than 70% of rated.
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| Operation with one pressure regulator out-of-service is only supported at power levels greater than 90% of rated and less than 50% of rated.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 3 120.0 110.0 100.0 90.0 MELLLA+
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| 80.0 MELLLA 70.0
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| % Power 60.0 50.0 I C
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| F 40.0 30.0 20.0 Natural Circulation 10.0 Line Minimum Power Line 35% Minimum Pump 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 0 10 20 30 40 50 60 70 80 90 100 110 120 (%)
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| Core Flow Figure 1.1 Brunswick Unit 1 Power/Flow Map
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 4 2.0 DISPOSITION OF EVENTS AND PLANT MODELING SENSITIVITIES 2.1 Disposition of Events for ATRIUM 11 Fuel Introduction A disposition of events to identify the limiting events which need to be analyzed to support operation at the Brunswick Steam Electric Plant was performed for the introduction of ATRIUM 11 fuel. Events and analyses identified as potentially limiting were either evaluated generically for the introduction of ATRIUM 11 fuel or are performed on a cycle-specific basis.
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| The first step in the disposition of events is to identify the licensing basis of the plant. Included in the licensing basis are descriptions of the postulated events/analyses and the associated criteria. Fuel-related system design criteria which must be met to ensure regulatory compliance and safe operation are also included. The BSEP licensing basis is contained in the Updated Final Safety Analysis Report (UFSAR), the Technical Specifications, Core Operating Limits Reports (COLR), and other reload analysis reports.
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| Framatome reviewed all the fuel-related design criteria, events, and analyses identified in the licensing basis. In many cases, when the operating limits are established to ensure acceptable consequences of an anticipated operational occurrence or accident, the fuel-related aspects of the system design criteria are met. All the fuel-related events were reviewed and dispositioned into one of the following categories:
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| * No further analysis required. This classification may result from one of the following:
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| The consequences of the event are bound by consequences of a different event.
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| The consequences of the event are benign, i.e., the event causes no significant change in margins to the operating limits.
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| The event is not affected by the introduction of a new fuel design and/or the current analysis of record remains applicable.
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| * Address event each reload. The consequences of the event are potentially limiting and need to be addressed each reload.
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| * Address for initial reload. This classification may result from one of the following:
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| The analysis is performed using conservative bounding assumptions and inputs such that the initial reload results will remain applicable for future reloads of the same fuel design.
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| Results from the first reload will be used to quantitatively demonstrate that the results remain applicable for future reloads of the same fuel design because the consequences are benign or bound by those of another event.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 5 The impacts of the EOOS scenarios presented in Table 1.1 were also considered in the disposition of events.
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| A summary of the disposition of events is presented in Tables 2.1 and 2.2. Table 2.1 presents a list of the events and analyses, the corresponding UFSAR section, the disposition status, and any applicable comments. Table 2.2 presents a summary of the disposition of events for the EOOS scenarios. Note that operation in the ICF and MELLLA+ regions of the power/flow map are included in the disposition results presented in Table 2.1.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 6 Table 2.1 Disposition of Events Summary for ATRIUM 11 Fuel Introduction at Brunswick UFSAR Section Event /Analysis Disposition Status Comments 3.9 Seismic Evaluation Address initial ATRIUM 11 fuel has been shown to reload. meet seismic analysis acceptance criteria.
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| 4.4 Thermal-Hydraulic Address initial ATRIUM 11 fuel has been shown to Compatibility reload. meet thermal-hydraulic compatibility acceptance criteria.
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| 4.4 Safety Limit MCPR Address each Required to establish operating limits.
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| reload.
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| 4.A Nuclear System Address each Required to establish operating limits.
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| Stability Analysis reload.
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| 5.2.2 Overpressurization Address each Potentially limiting event.
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| Protection reload.
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| 6.2.5 Combustible Gas No further Current analysis of record remains Control in analysis required. applicable.
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| Containment 9.1.1 New Fuel Storage Address for initial Evaluate for new fuel storage vault.
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| Criticality reload. Confirm applicability each reload. This issue is addressed in a separate report.
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| 9.1.2 Spent Fuel Storage Address for initial Evaluate for spent fuel pool. Confirm Criticality reload. applicability each reload. This issue is addressed in a separate report.
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| 9.3.4 Standby Liquid Address each Analysis performed to verify adequate Control (SLC) reload. SLC system shutdown capacity.
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| System 9.5.1 Fire Protection Address initial ATRIUM 11 fuel has been shown to Systems reload. meet Appendix R acceptance criteria.
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| 15.1.1 Loss of Feedwater Address each Potentially limiting AOO.
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| Heater (LFWH) reload.
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| 15.1.2 Feedwater Address each Potentially limiting AOO.
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| Controller Failure reload.
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| (FWCF) - Maximum Demand 15.1.3 Inadvertent HPCI No further Consequences bound by the FWCF.
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| or RCIC Pump analysis required.
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| Start
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 7 Table 2.1 Disposition of Events Summary for ATRIUM 11 Fuel Introduction at Brunswick (Continued)
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| UFSAR Section Event /Analysis Disposition Status Comments 15.1.4 Pressure Regulator No further Consequences bound by the TTNB.
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| Failure Open analysis required.
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| (PRFO) 15.1.5 Inadvertent No further Benign event.
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| Opening of a Relief analysis required.
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| Valve or Safety Valve 15.1.6 Inadvertent RHR No further Benign event.
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| Shutdown Cooling analysis required.
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| Operation 15.2.1 Generator Load Address each Potentially limiting AOO with bypass Rejection with and reload. inoperable.
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| without bypass (LRNB) 15.2.2 Turbine Trip with Address for initial Potentially limiting AOO. It is expected and without bypass reload. that results will show that this event is (TTNB) bound by LRNB.
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| 15.2.3 Main Steam No further Consequences bound by the LRNB Isolation Valve analysis required. and TTNB.
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| (MSIV) Closure 15.2.4 Loss of Condenser No further Consequences bound by the LRNB Vacuum analysis required. and TTNB.
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| 15.2.5 Loss of Auxiliary No further Consequences bound by the LRNB.
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| Power analysis required.
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| 15.2.6 Loss of Feedwater No further Benign event.
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| Flow analysis required.
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| 15.2.7 Loss of RHR No further Benign event.
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| Shutdown Cooling analysis required.
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| 15.2.8 Pressure Regulator No further Benign event with the backup Failure-Closed analysis required. pressure regulator in service.
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| 15.3.1 Recirculation Pump No further Benign event.
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| Trip analysis required.
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| 15.3.2 Recirculation Flow No further Benign event and bound by the trip of Control Failure - analysis required. one recirculation pump.
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| Decreasing Flow
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 8 Table 2.1 Disposition of Events Summary for ATRIUM 11 Fuel Introduction at Brunswick (Continued)
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| UFSAR Section Event /Analysis Disposition Status Comments 15.3.3 Recirculation Pump No further Consequences of the pump seizure Seizure analysis required. event are bound by other limiting rated power AOO events.
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| 15.4.1 Rod Withdrawal No further Benign event.
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| Error During Low analysis required.
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| Power Operation 15.4.2 Rod Withdrawal Address each Potentially limiting AOO.
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| Error at Power reload.
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| 15.4.3 Startup of Idle No further Nonlimiting event.
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| Recirculation Loop analysis required.
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| 15.4.4 Recirculation Flow No further Nonlimiting event.
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| Control Failure - analysis required.
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| Increasing Flow 15.4.5 Fuel Assembly No further Benign event.
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| Error During analysis required.
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| Refueling 15.4.6 Control Rod Drop Address each Potentially limiting accident.
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| Accident reload.
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| 15.6.3 Main Steam Line No further Fuel-related consequences bound by Break Accident analysis required. other LOCA events. Results of the current radiological release evaluation remain applicable.
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| 15.6.4 Loss of Coolant Address for initial Potentially limiting accident.
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| also 6.3 Accident (LOCA) reload.
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| 15.7.1 Refueling Accident Address for initial Potentially limiting accident.
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| reload.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 9 Table 2.1 Disposition of Events Summary for ATRIUM 11 Fuel Introduction at Brunswick (Continued)
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| UFSAR Section Event /Analysis Disposition Status Comments 15.8 Anticipated Address each Potentially limiting event. Over-Transient Without reload. pressurization analysis portion of the Scram event is expected for follow-on reloads.
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| Long term ATWS evaluations for suppression pool temperature and containment pressure requires
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| [
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| ].
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| PCT and MWR are bound by other analyses.
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| ATWS with core instability evaluations for ATRIUM 11 have been completed and meet acceptance criteria.
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| 15.9 Analytical Methods Address for initial Analyses that demonstrate the AST for Evaluating reload. evaluation is applicable to ATRIUM 11 Radiological Effects fuel have been completed.
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| With Alternative Source Term Slow Flow Runup Address each Analysis results are used to establish reload. the flow-dependent operating limits.
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| Backup Stability Address each Required to establish exclusion Protection reload. regions.
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| Mislocated or Address each Potentially limiting event.
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| Misoriented Fuel reload.
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| Assembly
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 10 Table 2.2 Disposition of Operating Flexibility and EOOS Options on Limiting Events Affected Limiting Option Events/Analyses Comments MSIV Out-of-Service Slow flow runup The impact of the increase in steam line pressure drop on the slow flow runup analysis will be evaluated each reload.
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| One SRV Out-of- ASME Overpressurization This scenario will be included as part of Service FWCF the base case condition for the events/analyses identified.
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| LRNB TTNB ATWS One ADS Valve LOCA The scenario will be included in the Out-of-Service break spectrum analyses (Reference 26) for the initial cycle.
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| FFTR/Feedwater Stability Solution This scenario will be examined each Heater Out-of- FWCF reload for most of these events Service /analyses. LRNB and TTNB events with LRNB reduced feedwater temperature will be TTNB evaluated for the initial reload.
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| Backup Stability Protection (BSP)
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| Single-Loop Operation LOCA The impact of SLO on LOCA will be (SLO) SLMCPR addressed for the initial cycle in the break spectrum analyses.
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| The SLO SLMCPR will be addressed each reload.
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| Turbine Bypass FWCF The FWCF event with TBVOOS will be Valves Out-of- evaluated each reload.
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| Service
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 11 Table 2.2 Disposition of Operating Flexibility and EOOS Options on Limiting Events (Continued)
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| Affected Limiting Option Events/Analyses Comments ICF/MELLLA+ ASME Overpressure For ATWS with core instabilities, analyses have been performed to show FWCF that ATRIUM 11 fuel will meet the LRNB appropriate acceptance criteria during TTNB MELLLA+ operation.
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| LOCA The remaining events need to be performed to cover the range of flows ATWS for MELLLA+.
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| SLMCPR Slow flow runup Stability Solutions
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 12 2.2 Plant Specific Modeling Sensitivities As part of the initial application of the AURORA-B AOO methodology to a plant, justification must be provided to ensure that conservative plant parameters are being used. This requirement is defined in Limitation and Conditions 7 and 11 of the Reference 19 safety evaluation. In particular, these limitations and conditions state:
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| : 7. As discussed in Section 3.6 of this SE, licensees should provide justification for the key plant parameters and initial conditions selected for performing sensitivity analyses on an event-specific basis. Licensees should further justify that the input values ultimately chosen for these key plant parameters and initial conditions will result in a conservative prediction of FoMs when performing calculations according to the AURORA-B EM described in ANP-10300P.
| |
| : 11. AREVA will provide justification for the uncertainties used for the highly ranked plant-specific PIRT parameters C12, R01, R02, and SL02 on a plant-specific basis, as described in Table 3.2 of this SE.
| |
| In order to comply with these requirements, a set of sensitivity studies was performed.
| |
| Separate sensitivity studies were performed for each of the three figures of merit that were required to license Brunswick Unit 1 Cycle 23: MCPR (Table 2.3), transient nodal power (Table 2.4), and overpressure (Table 2.5). These sensitivity studies address the key parameters required for licensing with the exception of C12 which is described below. In addition to these sensitivity studies, licensing calculations will also look at a wide range of core exposures and flow rates to ensure that the conservative statepoints have been analyzed.
| |
| Uncertainties associated with PIRT parameters R01, R02, and SL02 were evaluated for the initial transition. [
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| ]
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 13
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 14 Limitation and Condition 16 of the Reference 19 SE, given below, also requires a plant specific justification.
| |
| : 16. [ ] is not sampled as part of the methodology, justification should be provided on a plant-specific basis that a conservative flow rate has been assumed [
| |
| ].
| |
| The [ ] is provided by Duke and accounts for [
| |
| ]. The AURORA-B model [
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| ]
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 15 Table 2.3 Plant Parameter Sensitivity Results for MCPR
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 16 Table 2.3 Plant Parameter Sensitivity Results for MCPR (continued)
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 17 Table 2.3 Plant Parameter Sensitivity Results for MCPR (continued)
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 18 Table 2.3 Plant Parameter Sensitivity Results for MCPR (continued)
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 19 Table 2.4 Plant Parameter Sensitivity Results for Transient Nodal Power
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 20 Table 2.4 Plant Parameter Sensitivity Results for Transient Nodal Power (continued)
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 21 Table 2.4 Plant Parameter Sensitivity Results for Transient Nodal Power (continued)
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 22 Table 2.4 Plant Parameter Sensitivity Results for Transient Nodal Power (continued)
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 23 Table 2.5 Plant Parameter Sensitivity Results for Overpressurization
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 24 Table 2.5 Plant Parameter Sensitivity Results for Overpressurization (continued)
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 25 Table 2.5 Plant Parameter Sensitivity Results for Overpressurization (continued)
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 26 3.0 MECHANICAL DESIGN ANALYSIS The mechanical design analyses for ATRIUM 10XM and ATRIUM 11 fuel assemblies are presented in the applicable mechanical design reports (References 5, 6, 7, and 36). The maximum exposure limits for the ATRIUM 10XM and ATRIUM 11 fuel designs are:
| |
| 54.0 GWd/MTU average assembly exposure (ATRIUM 10XM) 57.0 GWd/MTU average assembly exposure (ATRIUM 11) 62.0 GWd/MTU rod average exposure (full-length fuel rods)
| |
| The ATRIUM 10XM and ATRIUM 11 LHGR limits are presented in Section 8.0. The fuel cycle design analyses (Reference 3) have verified that the ATRIUM 10XM and ATRIUM 11 fuel assemblies remain within licensed burnup limits.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 27 4.0 THERMAL-HYDRAULIC DESIGN ANALYSIS 4.1 Thermal-Hydraulic Design and Compatibility The results of the thermal-hydraulic characterization and compatibility analyses are presented in the thermal-hydraulic design report (Reference 9). The analysis results demonstrate that the thermal-hydraulic design and compatibility criteria are satisfied for the Brunswick Unit 1 transition core consisting of ATRIUM 10XM and ATRIUM 11 fuel assemblies.
| |
| 4.2 Safety Limit MCPR Analysis The safety limit MCPR (SLMCPR) is defined as the minimum value of the critical power ratio which ensures that less than 0.1% of the fuel rods in the core are expected to experience boiling transition during normal operation or an anticipated operational occurrence (AOO). The SLMCPR for all fuel in the Brunswick Unit 1 Cycle 23 core was determined using the methodology described in Reference 10. The analysis was performed with a power distribution that conservatively represents expected reactor operating states that could both exist at the MCPR operating limit and produce a MCPR equal to the SLMCPR during an AOO.
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| The Brunswick Unit 1 Cycle 23 SLMCPR analysis used the ACE/ATRIUM 10XM critical power correlation additive constants and additive constant uncertainty described in Reference 11 for the ATRIUM 10XM fuel. The ACE/ATRIUM 11 critical power correlation, described in Reference 12, was applied to the ATRIUM 11 fuel assemblies.
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| In the Framatome methodology, the effects of channel bow on the critical power performance are accounted for in the SLMCPR analysis. Reference 10 discusses the application of a realistic channel bow model.
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| The fuel- and plant-related uncertainties used in the SLMCPR analysis are presented in Table 4.1. The radial power uncertainty used in the analysis includes 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 EFPH LPRM calibration interval. For TLO, analyses were performed for the minimum and maximum core flow conditions associated with rated power (85% and 104.5%), as well as the maximum core power at 55% core flow for the Brunswick power/flow map, Figure 1.1. For the maximum core flow statepoint, the TLO core flow uncertainty given in Table 4.1 was used. For the minimum core flow at full power, and 55% core flow statepoints, the SLO core flow uncertainty
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 28 in Table 4.1 was used consistent with the restrictions listed in Section 2.2.1.1 of the Reference 2 Safety Evaluation Report.
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| The analysis results support a two-loop operation (TLO) SLMCPR of 1.07 and a single-loop operation (SLO) SLMCPR of 1.09. Consistent with the approved Brunswick Unit 1 Technical Specification SLMCPR values, the Cycle 23 operating limits are based on SLMCPR values of 1.07 for TLO and 1.09 for SLO. Table 4.2 presents a summary of the analysis results including the SLMCPR and the percentage of rods expected to experience boiling transition.
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| 4.3 Core Hydrodynamic Stability Brunswick Unit 1 will implement a plant specific application of the Best-estimate Enhanced Option III (BEO-III) analysis methodology to support operation using the Confirmation Density Algorithm (CDA) as described in References 16 and 17. The CDA enabled through the OPRM system and the BSP solution described in References 16 and 17 will be the stability licensing basis for Brunswick. Cycle-specific analyses have been performed with RAMONA5-FA modeling recirculation pump trips from limiting MELLLA+, MELLLA with FWHOOS and SLO statepoints. The LPRM traces for limiting cases were analyzed with the CDA by Duke Energy consistent with the Reference 16 methodology. The minimum required TLO and SLO stability operating limits are 1.17 and 1.25, respectively. All cases with a channel decay ratio greater than 1.0 within the 95/95 population were confirmed to meet the requirements of the References 16 and 17 methodologies. The cycle-specific analyses have been performed consistent with the conditions provided by the NRC in Reference 37.
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| Analyses have shown that if shallow control blades (i.e. greater than Notch 36) are withdrawn, then the BEO-III acceptance criteria may not be met for ATRIUM 10XM fuel. Therefore, for Brunswick Unit 1 Cycle 23 operation, the control rods at a shallow position cannot be withdrawn further than their notch position specified in Reference 3. If this restriction cannot be met, the BEO-III with CDA analysis may nevertheless remain valid, but further assessment will be required.
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| The Backup Stability Protection (BSP) solution may be used by the plant in the event that the OPRM system is declared inoperable. Reference 16 Section 5 describes two BSP options that are based on selected elements from three distinct constituents: BSP Manual Regions, BSP Boundary, and Automated BSP (ABSP) setpoints.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 29 The Manual BSP region boundaries were validated for Brunswick Unit 1 Cycle 23 using STAIF (Reference 15 with modified fuel rod properties documented in Reference 17) for nominal and reduced feedwater temperature operation. The endpoints of the regions are defined in Table 4.3 and Table 4.4 for nominal and reduced feedwater temperature, respectively. The Manual BSP region boundary endpoints are connected using the Generic Shape Function (GSF).
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| The ABSP Average Power Range Monitor (APRM) Simulated Thermal Power (STP) setpoints associated with the ABSP Scram Region are listed in Table 4.5. These ABSP setpoints are applicable to both TLO and SLO as well as nominal and reduced feedwater temperature operation.
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| 4.4 Voiding in the Channel Bypass Region To demonstrate compliance with the NRCs requirement that there be less than 5% bypass voiding around the LPRMs (see Section 5.1.1.5.1 of the Reference 2 Safety Evaluation), the bypass void level has been evaluated throughout the cycle. The maximum bypass void value applicable to the Cycle 23 design [
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| ]
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| [
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| ]
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 30 Table 4.1 Fuel- and Plant-Related Uncertainties for Safety Limit MCPR Analyses Parameter Uncertainty Fuel-Related Uncertainties
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| [
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| ]
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| Plant-Related Uncertainties Feedwater flow rate 1.8%
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| Feedwater temperature 0.8%
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| Core pressure 0.8%
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| Total core flow rate TLO 2.5%
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| SLO 6%
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| [ ]
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 31 Table 4.2 Results Summary for Safety Limit MCPR Analyses Minimum Percentage Power/Flow Supported of Rods in Boiling
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| (%)
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| SLMCPR* Transition TLO - 1.07 0.0916
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| [ ]
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| TLO - 1.07 0.0916
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| [ ]
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| TLO - 1.07 0.0933
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| [ ]
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| SLO - 1.09 0.0790
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| [ ]
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| * The OLMCPR shown in Tables 8.1 through 8.9 were developed assuming a TLO SLMCPR of 1.07 and a SLO SLMCPR of 1.09.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 32 Table 4.3 BSP Endpoints For Nominal Feedwater Temperature Power Flow Endpoint Definition
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| (%) (%)
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| Scram Region A1 57.0 40.6 Boundary, HFCL Scram Region B1 42.0 31.7 Boundary, NCL Controlled Entry A2 64.5 50.0 Region Boundary, HFCL Controlled Entry B2 28.9 31.9 Region Boundary, NCL
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 33 Table 4.4 BSP Endpoints For Reduced Feedwater Temperature Power Flow Endpoint Definition
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| (%) (%)
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| Scram Region A1 65.9 51.8 Boundary, HFCL Scram Region B1 36.5 31.9 Boundary, NCL Controlled Entry A2 69.8 56.8 Region Boundary, HFCL Controlled Entry B2 28.9 31.9 Region Boundary, NCL
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 34 Table 4.5 ABSP Setpoints for the Scram Region Parameter Symbol Value Slope of ABSP APRM flow-mTRIP 2.00 %RTP/%RDF biased trip linear segment.
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| ABSP APRM flow-biased trip setpoint power intercept.
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| Constant Power Line for Trip PBSP-TRIP 42.0 %RTP from zero Drive Flow to Flow Breakpoint value.
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| ABSP APRM flow-biased trip setpoint drive flow intercept. WBSP-TRIP 37.5 %RDF Constant Flow Line for Trip.
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| Flow Breakpoint value WBSP-BREAK 25.0 %RDF
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 35 Table 4.6 Maximum Bypass Voiding at LPRM Level D*
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| Power (%) Cycle Bypass Flow (%) Exposure Void Condition (GWd/MTU) (%)
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| [ ]
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| * The voiding at LPRM level D bounds the voiding at LPRM levels A, B, and C.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 36 5.0 ANTICIPATED OPERATIONAL OCCURRENCES This section describes the analyses performed to determine the power- and flow-dependent MCPR operating limits for base case operation for Brunswick Unit 1 Cycle 23.
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| The AURORA-B methodology (Reference 19) is used with the Framatome THERMEX methodology (Reference 20) for the generation of thermal limits. AURORA-B is a comprehensive evaluation model developed for predicting the dynamic response of boiling water reactors (BWRs) during transient, postulated accident, and beyond design-basis accident scenarios. The evaluation model (EM) contains a multi-physics code system with flexibility to incorporate all the necessary elements for analysis of the full spectrum of BWR events that are postulated to affect the nuclear steam supply system of the BWR plant. Deterministic analysis principles are applied to satisfy plant operational and Technical Specification requirements through the use of conservative initial conditions and boundary conditions.
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| The foundation of AURORA-B AOO is built upon three computer codes, S-RELAP5, MB2-K, and RODEX4. Working together as a system, they make up the multi-physics evaluation model that provides the necessary systems, components, geometries, processes, etc. to assure adequate predictions of the relevant BWR event characteristics for its intended applications.
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| The three codes making up the foundation of the code system are:
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| * S-RELAP5 - This code provides the transient thermal-hydraulic, thermal conduction, control systems, and special process capabilities (i.e. valves, jet-pumps, steam separator, critical power correlations, etc.) necessary to simulate a BWR plant.
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| * MB2-K - This code uses advanced nodal expansion methods to solve the three-dimensional, two-group, neutron kinetics equations. The MB2-K code is consistent with the MICROBURN-B2 steady state core simulator. MB2-K receives a significant portion of its input from the steady state core simulator.
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| * RODEX4 - A subset of routines from this code are used to evaluate the transient thermal-mechanical fuel rod (including fuel/clad gap) properties as a function of temperature, rod internal pressure, etc. The fuel rod properties are used by S-RELAP5 when solving the transient thermal conduction equations in lieu of standard S-RELAP5 material property tables.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 37 The AURORA-B AOO methodology (Reference 19) includes an evaluation of the impact of code uncertainties on Figures of Merit (FoM) (e.g. MCPR, peak pressure) [
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| ] that has wide acceptance in the nuclear industry.
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| The ACE/ATRIUM 10XM critical power correlation (Reference 11) is used to evaluate the thermal margin for the ATRIUM 10XM fuel. The ACE/ATRIUM 11 critical power correlation (Reference 12) is used in the thermal margin evaluations for the ATRIUM 11 fuel.
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| 5.1 System Transients The reactor plant parameters for the system transient analyses were provided by the utility.
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| Analyses have been performed to determine power-dependent MCPR limits that protect operation throughout the power/flow domain shown in Figure 1.1.
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| At Brunswick, direct scram on turbine stop valve (TSV) position and turbine control valve (TCV) fast closure are bypassed at power levels less than 26% of rated (Pbypass). Scram will occur when the high pressure or high neutron flux scram setpoint is reached. Reference 22 indicates that MCPR limits only need to be monitored at power levels greater than or equal to 23% of rated, which is the lowest power analyzed for this report.
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| The limiting exposure for rated power pressurization transients is typically at end of full power (EOFP) when the control rods are fully withdrawn. The end-of-cycle licensing basis (EOCLB) analysis was performed at EOFP + 15 EFPD. Analyses were performed at cycle exposures prior to EOCLB to ensure that the operating limits provide the necessary protection. Analyses were also performed to support extended cycle operation with final feedwater temperature reduction (FFTR) and power coastdown. The Brunswick Unit 1 Cycle 23 licensing basis exposures used to develop the limits breakpoints are presented in Table 5.1.
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| All pressurization transients assumed that one of the lowest setpoint safety relief valves (SRV) was inoperable. This basis supports operation with 1 SRV out-of-service.
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| The Brunswick Unit 1 turbine bypass system includes four bypass valves. However, for base case analyses in which credit is taken for turbine bypass operation, only three of the turbine bypass valves are assumed operable.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 38 Reductions in feedwater temperature of less than or equal to 10°F from the nominal feedwater temperature and variation of +/- 10 psi in dome pressure are considered base case operation, not an EOOS condition. This decrease in feedwater temperature causes a small increase in the core inlet subcooling which changes the axial power shape and core void fraction. In addition, the steam flow for a given power level decreases since more power is used to increase the coolant enthalpy to saturated conditions. The consequences of the FWCF event can be more severe as a result of the increase in core inlet subcooling during the overcooling phase of the event. Analyses were performed to evaluate the impact of reduced feedwater temperature on the FWCF event. While a decrease in steam flow tends to make the LRNB event less severe, the TCV initial position is further closed which tends to make the event more severe, especially at higher power levels. LRNB and TTNB events for base case operation were evaluated for both nominal and 10°F reduced feedwater temperatures. The analyses were performed with the limiting feedwater and dome pressure conditions in the allowable ranges.
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| FFTR is used to extend rated power operation by decreasing the feedwater temperature. The amount of feedwater temperature reduction is a function of power with the maximum decrease of 110.3°F at rated power. Analyses were performed to support both nominal +/- 10 psi and constant rated dome pressure with combined FFTR/Coastdown operation to the maximum licensing exposure (Table 5.1). The FWCF analyses were performed with the lowest feedwater temperature associated with the initial power level. Operation with FFTR is not allowed in the MELLLA+ extension of the Brunswick operating domain.
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| The results of the system pressurization transients are sensitive to the scram speed used in the calculations. To take advantage of average scram speeds faster than those associated with the Technical Specifications requirements, scram speed-dependent MCPRp limits are provided. The nominal scram speed (NSS) insertion times, extended scram speed (ESS), and the Technical Specifications scram speed (TSSS) insertion times used in the analyses are presented in Table 5.2. The NSS or ESS MCPRp limits can only be applied if the scram speed test results meet their respective insertion times. System transient analyses were performed to establish MCPRp limits for NSS, ESS, and TSSS insertion times. The Brunswick Unit 1 Technical Specifications (Reference 22) allow for operation with up to 10 slow and 1 stuck control rod.
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| One additional control rod is assumed to fail to scram. The NSS, ESS, and TSSS analyses were performed to conservatively account for the effect of the slow and stuck rods on scram
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 39 reactivity. For transient events below 50% power without direct scram, the results are relatively insensitive to scram speed, and only TSSS analyses are performed.
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| Tables 5.10, 5.11, and 5.12 present the limiting LHGRFACp transient analysis results for base case operation used to develop the operating limits for NSS, ESS, and TSSS insertion times, respectively.
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| 5.1.1 Load Rejection No Bypass (LRNB)
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| The load rejection causes a fast closure of the turbine control valves. The resulting compression wave travels through the steam lines into the vessel and creates a rapid pressurization. The increase in pressure causes a decrease in core voids, which in turn causes a rapid increase in power. The fast closure of the turbine control valves also causes a reactor scram. Turbine bypass system operation, which also mitigates the consequences of the event, is not credited.
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| The excursion of the core power due to the void collapse is terminated primarily by the reactor scram and revoiding of the core.
| |
| For power levels less than 50% of rated, the LRNB analyses assume that the power load unbalance (PLU) is inoperable. With the PLU inoperable, the LRNB sequence of events is different than the standard event. Instead of a fast closure, the TCVs close in servo mode and there is no direct scram on TCV closure. The power and pressure excursion continues until the high pressure scram occurs. Given that there is no direct scram when the PLU is inoperable, the above and below Pbypass system responses at 26% power are identical.
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| LRNB analyses were performed for a range of power/flow conditions to support generation of the thermal limits. Tables 5.3, 5.4, and 5.5 present the base case limiting transient event and results as a function of power used to generate the EOCLB operating limits for NSS, ESS, and TSSS insertion times, respectively. Figures 5.1 - 5.3 show the responses of various reactor and plant parameters during the LRNB event initiated at 100% of rated power and 104.5% of rated core flow with TSSS insertion times at EOCLB.
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| 5.1.2 Turbine Trip No Bypass (TTNB)
| |
| The turbine trip causes a closure of the turbine stop valves. The resulting compression wave travels through the steam lines into the vessel and creates a rapid pressurization. The increase in pressure causes a decrease in core voids, which in turn causes a rapid increase in power.
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| The closure of the turbine stop valves also causes a reactor scram. Turbine bypass system
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 40 operation, which also mitigates the consequences of the event, is not credited. The excursion of the core power due to the void collapse is terminated primarily by the reactor scram and revoiding of the core.
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| TTNB analyses were performed for a range of power/flow conditions for which the TTNB event is potentially limiting to support generation of the thermal limits. Tables 5.3, 5.4, and 5.5 present the base case limiting transient event and results as a function of power used to generate the EOCLB operating limits for NSS, ESS, and TSSS insertion times, respectively. Figures 5.4 - 5.6 show the responses of various reactor and plant parameters during the TTNB event initiated at 100% of rated power and 104.5% of rated core flow with TSSS insertion times at EOCLB.
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| 5.1.3 Feedwater Controller Failure (FWCF)
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| The increase in feedwater flow due to a failure of the feedwater control system to maximum demand results in an increase in the water level and a decrease in the coolant temperature at the core inlet. The increase in core inlet subcooling causes an increase in core power. As the feedwater flow continues at maximum demand, the water level continues to rise and eventually reaches the high water level trip setpoint. The initial water level is conservatively assumed to be at the low-level normal operating range to delay the high-level trip and maximize the core inlet subcooling that results from the FWCF. The high water level trip causes the turbine stop valves to close in order to prevent damage to the turbine from excessive liquid inventory in the steam line. The valve closures create a compression wave that travels to the core causing a void collapse and subsequent rapid power excursion. The closure of the turbine stop valves also initiates a reactor scram. Three of the four installed turbine bypass valves are assumed operable and provide pressure relief. The core power excursion is mitigated in part by the pressure relief, but the primary mechanism for termination of the event is reactor scram.
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| FWCF analyses were performed for a range of power/flow conditions to support generation of the thermal limits. Tables 5.3, 5.4, and 5.5 present the base case limiting transient event and results as a function of power used to generate the EOCLB operating limits for NSS, ESS, and TSSS insertion times, respectively. Figures 5.7 - 5.9 show the responses of various reactor and plant parameters during the FWCF event initiated at 100% of rated power and 104.5% of rated core flow with TSSS insertion times at EOCLB.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 41 5.1.4 Pressure Regulator Failure Downscale (PRFDS)
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| The pressure regulator failure downscale event occurs when the pressure regulator system fails and sends a signal to close all four turbine control valves in control mode. Normally, a backup pressure regulator device would take control and maintain the setpoint pressure, resulting in a mild pressure excursion and a benign event. If 5 of the 6 pressure regulator devices were out-of-service, there would be no backup pressure regulator device and the event would be more severe. The core would pressurize resulting in void collapse and a subsequent power increase.
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| The event would be terminated by scram when either the high-neutron flux or high-pressure setpoint is reached. Operation with only one pressure regulator device is not supported for Brunswick Unit 1 over the entire power/flow map. However, Duke Energy requested that Framatome review the PRFDS event with one pressure device in service to determine if it is bound by the LRNB event at power levels greater than 90% of rated and less than 50% of rated.
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| Analysis results demonstrate that the LRNB is more limiting at power levels greater than 90% of rated. Since LRNB analyses assume the PLU is inoperable below 50% of rated power, the TCVs close in servo or control mode without a direct scram on fast closure. Therefore, the consequences of the PRFDS event with 5 of the 6 pressure regulators out of service are no more severe than the LRNB event at power levels less than 50% of rated.
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| 5.1.5 Loss of Feedwater Heating The loss of feedwater heating (LFWH) event analysis supports an assumed 100°F decrease in the feedwater temperature. The result is an increase in core inlet subcooling, which reduces voids, thereby increasing core power and shifting the axial power distribution toward the bottom of the core. As a result of the axial power shift and increased core power, voids begin to build up in the bottom region of the core, acting as negative feedback to the increased subcooling effect.
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| The negative feedback moderates the core power increase. Although there is a substantial increase in core thermal power during the event, the increase in steam flow is much less because a large part of the added power is used to overcome the increase in inlet subcooling.
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| The increase in steam flow is accommodated by the pressure control system via the TCVs or the turbine bypass valves, so no pressurization occurs. For Brunswick Unit 1 Cycle 23, a cycle-specific analysis was performed in accordance with the Reference 23 methodology to determine the change in MCPR for the event. The LFWH results are presented in Table 5.6.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 42 5.1.6 Control Rod Withdrawal Error The control rod withdrawal error (CRWE) transient is an inadvertent reactor operator initiated withdrawal of a control rod. This withdrawal increases local power and core thermal power, lowering the core MCPR. The CRWE transient is typically terminated by control rod blocks initiated by the rod block monitor (RBM). The CRWE event was analyzed assuming no xenon and allowing credible instrumentation out-of-service in the rod block monitor (RBM) system. The analysis further assumes that the plant could be operating in either an A or B sequence control rod pattern. The rated power CRWE results are shown in Table 5.7 for selected analytical RBM high power setpoint values from 108% to 117%. An assumed RBM high power setpoint of 111%
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| was used to develop the MCPRp limits. At the corresponding intermediate and lower power setpoint values, the MCPRp values bound, or are equal to, the CRWE MCPR values.
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| Framatome analyses show that standard filtered RBM setpoint reductions are supported.
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| Analyses demonstrate that the 1% strain and centerline melt criteria are met with the LHGR limits presented in Section 8.2. The recommended operability requirements based on the unblocked CRWE results are shown in Table 5.8 based on the SLMCPR values presented in Section 4.2.
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| 5.2 Slow Flow Runup Analysis Flow-dependent MCPR and LHGR limits are established to support operation at off-rated core flow conditions. The limits are based on the CPR and heat flux changes experienced by the fuel during slow flow excursions. The slow flow excursion event assumes a failure of the recirculation flow control system such that the core flow increases slowly to the maximum flow physically permitted by the equipment (107% of rated core flow). An uncontrolled increase in flow creates the potential for a significant increase in core power and heat flux. Operation with one MSIVOOS causes a larger increase in pressure and power during the flow excursion which results in a steeper flow runup path. A conservatively steep flow runup path was used in the analysis. The slow flow runup analyses were performed to support operation in all the EOOS scenarios.
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| XCOBRA is used to calculate the change in critical power ratio during a two-loop flow runup to the maximum flow rate. The MCPRf limit is set such that the increase in core power, resulting from the maximum increase in core flow, assures that the TLO safety limit MCPR is not violated.
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| Calculations were performed for a range of initial flow rates to determine the corresponding
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 43 MCPR values that put the limiting assembly on the safety limit MCPR at the high flow condition at the end of the flow excursion.
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| Results of the flow runup analysis are presented in Table 5.9. MCPRf limits that provide the required protection are presented in Table 8.10 and 8.11. The MCPRf limits are applicable for all Cycle 23 exposures.
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| Flow runup analyses were performed with CASMO-4/MICROBURN-B2 to determine flow-dependent LHGR multipliers (LHGRFACf) for ATRIUM 10XM and ATRIUM 11 fuel. The analysis assumes that the recirculation flow increases slowly along the limiting rod line to the maximum flow physically permitted by the equipment. A series of flow excursion analyses were performed at several exposures throughout the cycle starting from different initial power/flow conditions.
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| Xenon is assumed to remain constant during the event. The LHGRFACf multipliers are established to provide protection against fuel centerline melt and overstraining of the cladding during a flow runup. The Cycle 23 LHGRFACf multipliers are presented in Table 8.19.
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| The maximum flow during a flow excursion in single-loop operation is much less than the maximum flow during two-loop operation. Therefore, the flow-dependent MCPR limits and LHGR multipliers for two-loop operation are applicable for SLO.
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| 5.3 Equipment Out-of-Service Scenarios The equipment out-of-service (EOOS) scenarios supported for Brunswick Unit 1 Cycle 23 are presented in Table 1.1 and discussed further in the following subsections. Tables 5.10, 5.11, and 5.12 present the limiting LHGRFACp transient analysis results for each EOOS scenario used to develop the operating limits for NSS, ESS, and TSSS insertion times, respectively.
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| 5.3.1 FHOOS The FHOOS scenario assumes a feedwater temperature reduction of 110.3°F at rated power and steam flow. The effect of the reduced feedwater temperature is an increase in the core inlet subcooling which can change the axial power shape and core void fraction. In addition, the steam flow for a given power level decreases since more power is required to increase the enthalpy of the coolant to saturated conditions. The consequences of the FWCF event are potentially more severe as a result of the increase in core inlet subcooling during the overcooling phase of the event. While the decrease in steam flow tends to make the LRNB event less severe, the TCV initial position is further closed which tends to make the event more
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 44 severe, especially at higher power levels. FWCF events were analyzed to ensure that appropriate FHOOS operating limits are established. Operation with FHOOS or the related FFTR scenario is not allowed in the MELLLA+ region.
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| 5.3.2 TBVOOS For this EOOS scenario, operation with TBVOOS means that the fast opening capability of two or more of the turbine bypass valves cannot be assured, thereby reducing the pressure relief capacity during fast pressurization transients. While the base case LRNB and TTNB events are analyzed assuming the turbine bypass valves out-of-service, operation with TBVOOS has an adverse effect on the FWCF event. Analyses of the FWCF event with TBVOOS were performed to establish the TBVOOS operating limits.
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| 5.3.3 Combined FHOOS and TBVOOS FWCF analyses with both FHOOS and TBVOOS were performed. Operating limits for this combined EOOS scenario were established using these FWCF results. This scenario is not allowed in the MELLLA+ region.
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| 5.3.4 One SRVOOS As noted earlier, all pressurization transient analyses were performed with one of the lowest setpoint SRVs assumed inoperable. Therefore, the base case operating limits support operation with one SRVOOS. The EOOS operating limits also support operation with one SRVOOS.
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| 5.3.5 One MSIVOOS Operation with one MSIVOOS is supported for operation less than 70% of rated power. At these reduced power levels, the flow through any one steam line will not be greater than the flow at rated power when all MSIVs are available. Since all four turbine control valves are available, adequate pressure control can be maintained. The main difference in operation with one MSIVOOS is that the steam line pressure drop between the steam dome and the turbine valves is higher than if all MSIVs are available. Since low steam line pressure drop is limiting for pressurization transients, the results of the pressurization events with all MSIVs in service bound the results with one MSIVOOS. In addition, operation with one MSIVOOS has no impact on the other nonpressurization events evaluated to establish power-dependent operating limits.
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| Therefore, the power-dependent operating limits applicable to base case operation with all
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 45 MSIVs in service remain applicable for operation with one MSIVOOS for power levels less than or equal to 70% of rated. As noted earlier, slow flow runup analyses were performed to support operation with one MSIVOOS.
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| 5.3.6 Single-Loop Operation Operation in SLO is only supported up to a maximum core flow of 45 Mlbm/hr which corresponds to a maximum power level of 71.1% of rated at the MELLLA boundary. In SLO, the two-loop operation limiting MCPRs and LHGRFAC multipliers remain applicable. The only impacts on the MCPR, LHGR, and MAPLHGR limits for SLO are an increase of 0.02 in the SLMCPR as discussed in Section 4.2, and the application of an SLO MAPLHGR multiplier discussed in Section 8.3. The net result is a 0.02 increase in the base case MCPRp limits and a decrease in the MAPLHGR limit. The same situation is true for the EOOS scenarios. Adding 0.02 to the corresponding two-loop operation EOOS MCPRp limits results in SLO MCPRp limits for the EOOS conditions. The TLO EOOS LHGRFAC multipliers remain applicable in SLO. This scenario is not allowed in the MELLLA+ region.
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| 5.4 Licensing Power Shape The licensing axial power profile used by Framatome for the plant transient analyses bounds the projected end of full power axial power profile. The conservative licensing axial power profile generated at the EOCLB core average exposure of 35,829 MWd/MTU is given in Table 5.13.
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| Cycle 23 operation is considered to be in compliance when:
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| * The integrated normalized power generated in the bottom 7 nodes from the projected EOFP solution at the state conditions provided in Table 5.13 is greater than the integrated normalized power generated in the bottom 7 nodes in the licensing basis axial power profile, and the individual normalized power from the projected EOFP solution is greater than the corresponding normalized power from the licensing basis axial power profile for at least 6 of the 7 bottom nodes.
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| * The projected EOFP condition occurs at a core average exposure less than or equal to EOCLB.
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| If the criteria cannot be fully met, the licensing basis may nevertheless remain valid but further assessment will be required.
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| The licensing basis power profile in Table 5.13 was calculated using the MICROBURN-B2 code.
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| Compliance analyses must also be performed using MICROBURN-B2. Note that the power profile comparison should be done without incorporating instrument updates to the axial profile
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 46 because the updated power is not used in the core monitoring system to accumulate assembly burnups.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 47 Table 5.1 Exposure Basis for Brunswick Unit 1 Cycle 23 Transient Analysis Cycle Core Exposure at Average End of Interval Exposure (MWd/MTU) (MWd/MTU)* Comments 0 16,658 Beginning of cycle 16,000 32,658 Break point for exposure-dependent MCPRp limits (NEOC) 19,171 35,829 Design basis rod patterns to EOFP + 15 EFPD (EOCLB) 20,697 37,355 Maximum licensing core exposure - including FFTR
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| /Coastdown
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| * Note that the limits presented in Tables 8.1 - 8.9 and Tables 8.13 - 8.18 are based on core average exposure.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 48 Table 5.2 Scram Speed Insertion Times Control Rod TSSS ESS NSS Position Time Time Time (notch) (sec) (sec) (sec) 48 (full-out) 0.000 0.000 0.000 48 0.200 0.200 0.200 46 0.440 0.326 0.303 36 1.080 0.853 0.814 26 1.830 1.419 1.351 6 3.350 2.586 2.466 0 (full-in) 3.806 2.936 2.800
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 49 Table 5.3 EOCLB Base Case Limiting Transient Event NSS Insertion Time ATRIUM 10XM Limiting ATRIUM 11 Limiting Power MCPR Event MCPR Event 100 0.29 LRNB 0.31 TTNB 90 0.29 LRNB 0.33 LRNB 80 0.32 LRNB 0.37 LRNB 70 0.36 LRNB 0.42 LRNB 60 0.38 LRNB 0.44 LRNB 50 0.44 FWCF 0.54 FWCF 50 at > 65%F PLU inoperable 0.74 LRNB 0.77 LRNB 50 at 65%F PLU inoperable 0.62 LRNB 0.54 LRNB 30 1.05 LRNB 1.03 LRNB 26 at > 65%F PLU inoperable 1.08 LRNB 1.05 LRNB 26 at 65%F PLU inoperable 0.91 LRNB 0.83 LRNB 26 at > 65%F below Pbypass 1.15 FWCF 1.16 FWCF 26 at 65%F below Pbypass 1.10 FWCF 1.06 FWCF 23 at > 65%F below Pbypass 1.27 FWCF 1.18 FWCF 23 at 65%F below Pbypass 1.27 FWCF 1.18 FWCF
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 50 Table 5.4 EOCLB Base Case Limiting Transient Event ESS Insertion Time ATRIUM 10XM Limiting ATRIUM 11 Limiting Power MCPR Event MCPR Event 100 0.29 LRNB 0.32 TTNB 90 0.29 LRNB 0.33 LRNB 80 0.32 LRNB 0.37 LRNB 70 0.36 LRNB 0.42 LRNB 60 0.38 LRNB 0.44 LRNB 50 0.44 FWCF 0.54 FWCF 50 at > 65%F PLU inoperable 0.74 LRNB 0.77 LRNB 50 at 65%F PLU inoperable 0.62 LRNB 0.54 LRNB 30 1.05 LRNB 1.03 LRNB 26 at > 65%F PLU inoperable 1.08 LRNB 1.05 LRNB 26 at 65%F PLU inoperable 0.91 LRNB 0.83 LRNB 26 at > 65%F below Pbypass 1.15 FWCF 1.16 FWCF 26 at 65%F below Pbypass 1.10 FWCF 1.06 FWCF 23 at > 65%F below Pbypass 1.27 FWCF 1.18 FWCF 23 at 65%F below Pbypass 1.27 FWCF 1.18 FWCF
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 51 Table 5.5 EOCLB Base Case Limiting Transient Event TSSS Insertion Time ATRIUM 10XM Limiting ATRIUM 11 Limiting Power MCPR Event MCPR Event 100 0.38 LRNB 0.41 LRNB 90 0.37 LRNB 0.39 LRNB 80 0.39 LRNB 0.45 LRNB 70 0.43 LRNB 0.52 LRNB 60 0.45 LRNB 0.56 LRNB 50 0.58 LRNB 0.61 LRNB 50 at > 65%F PLU inoperable 0.74 LRNB 0.77 LRNB 50 at 65%F PLU inoperable 0.62 LRNB 0.54 LRNB 30 1.05 LRNB 1.03 LRNB 26 at > 65%F PLU inoperable 1.08 LRNB 1.05 LRNB 26 at 65%F PLU inoperable 0.91 LRNB 0.83 LRNB 26 at > 65%F below Pbypass 1.15 FWCF 1.16 FWCF 26 at 65%F below Pbypass 1.10 FWCF 1.06 FWCF 23 at > 65%F below Pbypass 1.27 FWCF 1.18 FWCF 23 at 65%F below Pbypass 1.27 FWCF 1.18 FWCF
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 52 Table 5.6 Loss of Feedwater Heating Transient Analysis Results Power ATRIUM 10XM ATRIUM 11
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| (% rated) CPR CPR 100 0.15 0.17 90 0.15 0.18 80 0.16 0.18 70 0.17 0.19 60 0.18 0.21 50 0.20 0.23 40 0.23 0.26 30 0.28 0.31 23 0.34 0.37 Table 5.7 Control Rod Withdrawal Error CPR Results Analytical RBM Setpoint (without filter) ATRIUM 10XM ATRIUM 11
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| (%) CPR CPR 108 0.22 0.20 111 0.27 0.23 114 0.30 0.25 117 0.40 0.33
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 53 Table 5.8 RBM Operability Requirements Applicable Applicable Thermal Power ATRIUM 10XM ATRIUM 11
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| (% rated) OLMCPR OLMCPR 1.59 TLO 1.49 TLO 29% and < 90% 1.62 SLO 1.52 SLO 90% 1.49 TLO 1.42 TLO Table 5.9 Flow-Dependent MCPR Results Core ATRIUM 10XM ATRIUM 10XM ATRIUM 11 ATRIUM 11 Flow Limiting MCPR Limiting MCPR Limiting MCPR Limiting MCPR
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| (% rated) MSIVIS MSIVOOS MSIVIS MSIVOOS 31 1.47 1.65 1.40 1.55 40 1.42 1.56 1.33 1.45 50 1.41 1.53 1.30 1.39 60 1.39 1.47 1.27 1.34 70 1.32 1.38 1.24 1.29 80 1.24 1.29 1.20 1.24 90 1.20 1.23 1.17 1.19 100 1.14 1.16 1.12 1.13 107 1.10 1.10 1.08 1.08
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 54 Table 5.10 EOCLB LHGRFACp Transient Results NSS Insertion Time Base FHOOS/
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| Power Case FHOOS TBVOOS TBVOOS ATRIUM 11 Fuel 100 1.00 1.00 1.00 0.98 90 1.00 1.00 1.00 0.97 50 0.96 0.91 0.92 0.88 50 at > 65%F PLU inoperable 0.85 0.85 0.85 0.85 50 at 65%F PLU inoperable 0.93 0.93 0.93 0.93 26 at > 65%F PLU inoperable 0.67 0.67 0.67 0.67 26 at 65%F PLU inoperable 0.79 0.79 0.79 0.79 26 at > 65%F below Pbypass 0.46 0.44 0.41 0.37 26 at 65%F below Pbypass 0.48 0.46 0.48 0.46 23 at > 65%F below Pbypass 0.46 0.43 0.37 0.34 23 at 65%F below Pbypass 0.48 0.45 0.45 0.42 ATRIUM 10XM Fuel 100 1.00 1.00 1.00 1.00 90 1.00 1.00 1.00 1.00 50 1.00 1.00 1.00 0.96 50 at > 65%F PLU inoperable 0.92 0.92 0.92 0.92 50 at 65%F PLU inoperable 1.00 1.00 1.00 1.00 26 at > 65%F PLU inoperable 0.75 0.75 0.75 0.75 26 at 65%F PLU inoperable 0.86 0.86 0.86 0.86 26 at > 65%F below Pbypass 0.50 0.48 0.45 0.42 26 at 65%F below Pbypass 0.51 0.49 0.51 0.49 23 at > 65%F below Pbypass 0.50 0.47 0.41 0.38 23 at 65%F below Pbypass 0.51 0.49 0.50 0.47
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 55 Table 5.11 EOCLB LHGRFACp Transient Results ESS Insertion Time Base FHOOS/
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| Power Case FHOOS TBVOOS TBVOOS ATRIUM 11 Fuel 100 1.00 1.00 1.00 0.97 90 1.00 1.00 1.00 0.97 50 0.96 0.91 0.92 0.88 50 at > 65%F PLU inoperable 0.85 0.85 0.85 0.85 50 at 65%F PLU inoperable 0.93 0.93 0.93 0.93 26 at > 65%F PLU inoperable 0.67 0.67 0.67 0.67 26 at 65%F PLU inoperable 0.79 0.79 0.79 0.79 26 at > 65%F below Pbypass 0.46 0.44 0.41 0.37 26 at 65%F below Pbypass 0.48 0.46 0.48 0.46 23 at > 65%F below Pbypass 0.46 0.43 0.37 0.34 23 at 65%F below Pbypass 0.48 0.45 0.45 0.42 ATRIUM 10XM Fuel 100 1.00 1.00 1.00 1.00 90 1.00 1.00 1.00 1.00 50 1.00 1.00 1.00 0.96 50 at > 65%F PLU inoperable 0.92 0.92 0.92 0.92 50 at 65%F PLU inoperable 1.00 1.00 1.00 1.00 26 at > 65%F PLU inoperable 0.75 0.75 0.75 0.75 26 at 65%F PLU inoperable 0.86 0.86 0.86 0.86 26 at > 65%F below Pbypass 0.50 0.48 0.45 0.42 26 at 65%F below Pbypass 0.51 0.49 0.51 0.49 23 at > 65%F below Pbypass 0.50 0.47 0.41 0.38 23 at 65%F below Pbypass 0.51 0.49 0.50 0.47
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 56 Table 5.12 EOCLB LHGRFACp Transient Results TSSS Insertion Time Base FHOOS/
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| Power Case FHOOS TBVOOS TBVOOS ATRIUM 11 Fuel 100 1.00 0.96 0.99 0.94 90 -- -- -- --
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| 50 0.93 0.88 0.87 0.83 50 at > 65%F PLU inoperable 0.85 0.85 0.85 0.83 50 at 65%F PLU inoperable 0.93 0.93 0.93 0.93 26 at > 65%F PLU inoperable 0.67 0.67 0.67 0.67 26 at 65%F PLU inoperable 0.79 0.79 0.79 0.79 26 at > 65%F below Pbypass 0.46 0.44 0.41 0.37 26 at 65%F below Pbypass 0.48 0.46 0.48 0.46 23 at > 65%F below Pbypass 0.46 0.43 0.37 0.34 23 at 65%F below Pbypass 0.48 0.45 0.45 0.42 ATRIUM 10XM Fuel 100 1.00 1.00 1.00 1.00 90 1.00 1.00 1.00 1.00 50 1.00 0.96 0.95 0.91 50 at > 65%F PLU inoperable 0.92 0.92 0.92 0.91 50 at 65%F PLU inoperable 1.00 1.00 1.00 1.00 26 at > 65%F PLU inoperable 0.75 0.75 0.75 0.75 26 at 65%F PLU inoperable 0.86 0.86 0.86 0.86 26 at > 65%F below Pbypass 0.50 0.48 0.45 0.42 26 at 65%F below Pbypass 0.51 0.49 0.51 0.49 23 at > 65%F below Pbypass 0.50 0.47 0.41 0.38 23 at 65%F below Pbypass 0.51 0.49 0.50 0.47
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 57 Table 5.13 Licensing Basis Core Average Axial Power Profile State Conditions for Power Shape Evaluation Power, MWt 2923.0 MICROBURN-B2 pressure, psia 1044.8 Inlet subcooling, Btu/lbm 20.3 Flow, Mlb/hr 80.5 Control state ARO Core average exposure (EOCLB), MWd/MTU 35,829 Licensing Axial Power Profile (Normalized)
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| Node Power Top 25 0.273 24 0.609 23 1.010 22 1.197 21 1.304 20 1.384 19 1.416 18 1.437 17 1.428 16 1.399 15 1.392 14 1.342 13 1.365 12 1.320 11 1.242 10 1.195 9 1.119 8 1.010 7 0.887 6 0.756 5 0.617 4 0.493 3 0.402 2 0.310 Bottom 1 0.091
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 58 Figure 5.1 EOCLB LRNB at 100P/104.5F - TSSS Key Parameters
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 59 Figure 5.2 EOCLB LRNB at 100P/104.5F - TSSS Sensed Water Level
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 60 Figure 5.3 EOCLB LRNB at 100P/104.5F - TSSS Vessel Pressures
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 61 Figure 5.4 EOCLB TTNB at 100P/104.5F - TSSS Key Parameters
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 62 Figure 5.5 EOCLB TTNB at 100P/104.5F - TSSS Sensed Water Level
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 63 Figure 5.6 EOCLB TTNB at 100P/104.5F - TSSS Vessel Pressures
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 64 Figure 5.7 EOCLB FWCF at 100P/104.5F - TSSS Key Parameters
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 65 Figure 5.8 EOCLB FWCF at 100P/104.5F - TSSS Sensed Water Level
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 66 Figure 5.9 EOCLB FWCF at 100P/104.5F - TSSS Vessel Pressures
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 67 6.0 POSTULATED ACCIDENTS 6.1 Loss-of-Coolant Accident (LOCA)
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| The results of the ATRIUM 10XM LOCA analysis are presented in References 24 and 25 and provide a PCT of 1923°F, as supplemented by Reference 27. The peak local metal water reaction is 1.23% and the core wide metal water reaction is < 0.56%. The SLO MAPLHGR multiplier is 0.80; however SLO is not allowed when operating in the MELLLA+ domain. The cycle-specific OLMCPRs and off-rated flow dependent LHGR setdown bounds those assumed in References 24 and 25.
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| A LOCA evaluation was performed for the ATRIUM 11 fuel for MELLLA+ operation and the results are presented in Reference 26. The ATRIUM 11 PCT is 1957°F, occurring at 0.0 MWd/MTU. The peak local metal water reaction is 4.75% and the core wide metal water reaction is 0.41%. The ATRIUM 11 SLO MAPLHGR multiplier is 0.85. The cycle-specific OLMCPRs and off-rated flow dependent LHGR setdown bounds those assumed in Reference
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| : 26. The ATRIUM 11 LOCA analyses are based on the [
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| ]
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| The Brunswick LOCA radiological analysis implementing the alternative source term methodology was performed in consideration of ATRIUM 10XM and ATRIUM 11 fuel in the core inventory source terms. Duke Energy has evaluated the radiological consequences of a LOCA and determined ATRIUM 10XM and ATRIUM 11 fuel meets the applicable acceptance criteria for Brunswick Unit 1 Cycle 23.
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| 6.2 Control Rod Drop Accident (CRDA)
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| Brunswick Unit 1 uses a bank position withdrawal sequence (BPWS) including reduced notch worth rod pull to limit high worth control rod movements. The CRDA evaluation is performed for both A and B sequence startups consistent with the withdrawal sequence specified by Duke Energy. Framatomes AURORA-B CRDA methodology (Reference 32) is used. The applicability of this methodology for the Brunswick plant is demonstrated in Reference 33.
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| The analysis utilized the current Brunswick failure criteria as well as that proposed in draft guidance (DG-1327 Reference 34). The failure criterion of DG-1327 protects the existing failure criteria used by the Brunswick station. The CRDA analysis results demonstrate that the core
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 68 coolability is maintained with total fuel enthalpy remaining below 230 cal/g and no fuel melting.
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| The radiological consequences are shown to be bounded by the Brunswick CRDA AST analysis.
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| The following table identifies the limiting rod drop with the actual number of rod failures and the number of rod failures scaled up to account for the revised release fractions of DG-1327*
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| compared to those of RG 1.183. Duke Energy has determined the radiological release assumed in the current Brunswick CRDA AST analysis bounds 955 rod failures for core source terms based on ATRIUM 10XM fuel and 1129 rod failures for core source terms based on ATRIUM 11 (Reference 35).
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| ATRIUM 10XM ATRIUM 11 Max BRK BRK Max Fraction of Prompt Bundles Actual FSAR Actual FSAR Total Fuel Allowed Sequence Enthalpy with Rod Dose- Rod Dose-Enthalpy Melting Rod Increase Failures Failures Equivalent Failures Equivalent (cal / g) Failures (cal / g) Failures Failures B1234 191.99 207.06 no 4 8 11 104 154 0.15§ B1243 6.3 Fuel and Equipment Handling Accident Duke Energy has determined the radiological release assumed in the current fuel handling accident (FHA) analysis implementing the AST methodology bounds 161 rod failures for core source terms based on ATRIUM 10XM fuel. Framatome has performed an analysis that shows that the number of failed fuel rods due to a fuel handling accident involving the ATRIUM 10XM
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| * Results are provided using the criteria specified in the Reference 34 version of DG-1327 which is consistent with the criteria previously used in ANP-3714P (Reference 33).
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| The actual numbers of rod failures are the total unique rod failures from the PCMI, high temperature, and fuel melt criteria.
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| The FSAR dose-equivalent rod failures account for the difference in release fraction between those used in the Brunswick plant licensing based on RG 1.183 and a conservative scaling based on revised release fractions proposed in DG-1327. These scaled values account for revision in calculation method for transient fission gas release fraction (Reference 35).
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| § Dose-equivalent fuel rod failures from each fuel type are counted toward their number of allowed failures individually and those fractions are summed to give an effective total fraction of failed fuel rods.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 69 fuel is 161. These results are consistent with the number of failed rods supported by the current Brunswick AST analysis.
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| Framatome has also performed an analysis that shows that the number of failed fuel rods due to a fuel handling accident involving the ATRIUM 11 fuel does not exceed 194. These results are consistent with the number of failed rods supported by the current Brunswick AST analysis.
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| 6.4 Fuel Loading Error (Infrequent Event)
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| There are two types of fuel loading errors possible in a BWR: the mislocation of a fuel assembly in a core position prescribed to be loaded with another fuel assembly, and the misorientation of a fuel assembly with respect to the control blade. As described in Reference 14, the fuel loading error is characterized as an infrequent event. The acceptance criteria are that the offsite dose consequences due to the event shall not exceed a small fraction of the 10 CFR 50.67 limits.
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| 6.4.1 Mislocated Fuel Bundle Framatome has performed a fuel mislocation error analysis for Brunswick Unit 1 Cycle 23. This analysis evaluated the impact of a mislocated assembly against potential fuel rod failure mechanisms due to increased LHGR and reduced CPR. Based on this analysis, the offsite dose criteria (a small fraction of 10 CFR 50.67) is conservatively satisfied. A dose consequence evaluation is not necessary since no rod approached the fuel centerline melt or 1% strain limits, and less than 0.1% of the fuel rods are expected to experience boiling transition which could result in a dryout induced failure.
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| 6.4.2 Misoriented Fuel Bundle Framatome has performed a fuel assembly misorientation analysis for all fuel assemblies in Brunswick Unit 1 Cycle 23 (monitored with the ACE critical power correlation). The analysis was performed assuming that the limiting assembly was loaded in the worst orientation (rotated 180°) and depleted through the cycle without operator interaction. The analysis demonstrates that the small fraction of 10 CFR 50.67 offsite dose criteria is conservatively satisfied. A dose consequence evaluation is not necessary since no rod approached the fuel centerline melt or 1% strain limits and less than 0.1% of the fuel rods are expected to experience boiling transition.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 70 7.0 SPECIAL ANALYSES 7.1 ASME Overpressurization Analysis This section describes the maximum overpressurization analyses performed to demonstrate compliance with the ASME Boiler and Pressure Vessel Code. The analysis shows that the safety/relief valves at Brunswick Unit 1 have sufficient capacity and performance to prevent the reactor vessel pressure from reaching the safety limit of 110% of the design pressure.
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| For Brunswick Unit 1 Cycle 23, a set of MSIV closure runs were first performed for 102% power and 104.5% flow and 85% flow at the highest Cycle 23 exposure where rated power operation can be attained. The MSIV closure event is similar to the other steam line valve closure events in that the valve closure results in a rapid pressurization of the core. The increase in pressure causes a decrease in void which in turn causes a rapid increase in power. The turbine bypass valves do not impact the system response and are not modeled in the analysis. [
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| ] The following assumptions were made in the analysis:
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| * The most critical active component (direct scram on valve position) was assumed to fail.
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| However, scram on high neutron flux and high dome pressure is available.
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| * The plant configuration analyzed assumed degraded lift setpoints of the limiting bank of SRVs (Reference 4, Item V.A). The SRV degradation scheme is based on actual plant performance using a 95/95 approach which bounds the 3% Technical Specifications requirement. In addition, one of the lowest setpoint SRVs is assumed inoperable.
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| * TSSS insertion times were used.
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| * The initial dome pressure was set at the maximum allowed by the Technical Specifications, 1059.7 psia (1045 psig).
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| * A fast MSIV closure time of 2.7 seconds was used.
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| Results of the limiting MSIV closure overpressurization analysis are presented in Table 7.1.
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| Figures 7.1 - 7.4 show the response of various reactor plant parameters during the MSIV closure event. The maximum pressure of 1344 psig occurs in the lower plenum. The maximum dome pressure for the same event is 1310 psig. The results demonstrate that the maximum vessel pressure limit of 1375 psig and dome pressure limit of 1325 psig are not exceeded.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 71 7.2 ATWS Event Evaluation 7.2.1 ATWS Overpressurization Analysis This section describes the analyses performed to demonstrate that the peak vessel pressure for the limiting ATWS event is less than the ASME Service Level C limit of 120% of the design pressure (1500 psig). The ATWS overpressurization analyses were performed at 100% power at 85% and 104.5% flow. The MSIV closure and pressure regulator failure open (PRFO) events were evaluated. Failure of the pressure regulator in the open position causes the turbine control and turbine bypass valves to open such that steam flow increases until the maximum combined steam flow limit is attained. The system pressure decreases until the low pressure setpoint is reached, resulting in the closure of the MSIVs. The resulting pressurization wave causes a decrease in core voids and an increase in core pressure thereby increasing the core power. For the MSIV closure event, the event is initiated by a fast closure of the MSIVs. This results in a pressurization wave that causes a decrease in core voids which results in an increase in core power and pressure.
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| [
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| ]
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| The following assumptions were made in the analyses:
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| * The analytical limit ATWS-RPT setpoint and function were assumed.
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| * The plant configuration analyzed assumed degraded lift setpoints of the limiting bank of SRVs (Reference 4, Item V.B). The SRV degradation scheme is based on actual plant performance using a 95/95 approach which bounds the 3% Technical Specifications requirement. To support operation with one SRVOOS, the plant configuration analyzed assumed that one of the lowest setpoint SRVs was inoperable.
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| * All scram functions were disabled.
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| * The initial dome pressure was set to the nominal pressure with a -10 psi uncertainty (1035 psia).
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| * The MSIV closure is based on a nominal closure time of 4.0 seconds for both events.
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| Results of ATWS overpressurization analyses are presented in Table 7.2. Figures 7.5 - 7.8 show the response of various reactor plant parameters during the limiting MSIV closure event, the event which results in the maximum vessel pressure. The maximum lower plenum pressure
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 72 is 1461 psig and the maximum dome pressure is 1444 psig. The results demonstrate that the ATWS maximum vessel pressure limit of 1500 psig is not exceeded.
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| 7.2.2 Long-Term Evaluation Fuel design differences may impact the power and pressure excursion experienced during the ATWS event. This in turn may impact the amount of steam discharged to the suppression pool and containment. [
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| ] A review of the current licensing basis for Brunswick ATWS containment, which is a full core of ATRIUM 10XM fuel, shows that peak suppression pool temperature for MELLLA+
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| was 174 °F and the peak containment pressure was 8.4 psig, Section 9.3.1 of Reference 18.
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| [
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| ]
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| Relative to the 10 CFR 50.46 acceptance criteria (i.e., PCT and cladding oxidation), the consequences of an ATWS event are bound by those of the limiting LOCA event.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 73 7.2.3 ATWS with Core Instability The ATWS with core instability (ATWS-I) event was originally approved for ATRIUM 10XM in MELLLA+ at Brunswick in Reference 18. For ATRIUM 11 fuel, the Brunswick plant specific ATWS-I methodology, Reference 31 was used. The Brunswick ATRIUM 11 results given in Appendix F of Reference 31 demonstrate that the acceptance criteria are met.
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| 7.3 Standby Liquid Control System In the event that the control rod scram function becomes incapable of rendering the core in a shutdown state, the standby liquid control (SLC) system is required to be capable of bringing the reactor from full power to a cold shutdown condition at any time in the core life. The Brunswick Unit 1 SLC system is required to be able to inject 720 ppm natural boron equivalent at 70°F into the reactor coolant (including a 25% allowance for imperfect mixing, leakage, and volume of other piping connected to the reactor). An analysis that demonstrates that the SLC system meets the required shutdown capability for Cycle 23 has been performed. The analysis was performed to support a coolant temperature of 360.8°F with a boron concentration equivalent to 720 ppm at 70°F. The temperature of 360.8°F corresponds to the low pressure permissive for the RHR shutdown cooling suction valves, and represents the maximum reactivity condition with soluble boron in the coolant. The analysis shows the core to be subcritical throughout the cycle by at least 1.01% k.
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| 7.4 Fuel Criticality The new fuel storage vault criticality analysis for ATRIUM 11 fuel is presented in Reference 28.
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| The spent fuel pool criticality analysis for ATRIUM 11 fuel is presented in Reference 29. The ATRIUM 11 fuel assemblies identified for loading in Cycle 23 meet both the new and spent fuel storage requirements.
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| 7.5 Strongest Rod Out Shutdown Margin The BRK1-23 core has a minimum strongest rod out shutdown margin of 1.07 %k. This value is produced at the beginning of the cycle at the minimum coolant temperature condition (68°F).
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| This value assumes that BRK1-22 ended operation at the lowest allowable exposure.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 74 Table 7.1 ASME Overpressurization Analysis Results
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| * Maximum Vessel Peak Peak Pressure Maximum Neutron Heat Lower- Dome Flux Flux Plenum Pressure Event (% rated) (% rated) (psig) (psig)
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| MSIV closure 199 131 1344 1310 (102P/104.5F)
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| * The SRV degradation scheme is based on actual plant performance using a 95/95 approach.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 75 Table 7.2 ATWS Overpressurization Analysis Results
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| * Maximum Vessel Peak Peak Pressure Maximum Neutron Heat Lower- Dome Flux Flux Plenum Pressure Event (% rated) (% rated) (psig) (psig)
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| MSIV closure 223 159 1461 1444 (100P/85F)
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| * The SRV degradation scheme is based on actual plant performance using a 95/95 approach.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 76 Table 7.3 [
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| ]
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 77 Figure 7.1 MSIV Closure Overpressurization Event at 102P/104.5F - Key Parameters
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 78 Figure 7.2 MSIV Closure Overpressurization Event at 102P/104.5F - Sensed Water Level
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 79 Figure 7.3 MSIV Closure Overpressurization Event at 102P/104.5F - Vessel Pressures
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 80 Figure 7.4 MSIV Closure Overpressurization Event at 102P/104.5F - Safety/Relief Valve Flow Rates
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 81 Figure 7.5 MSIV ATWS Overpressurization Event at 100P/85F - Key Parameters
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 82 Figure 7.6 MSIV ATWS Overpressurization Event at 100P/85F - Sensed Water Level
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 83 Figure 7.7 MSIV ATWS Overpressurization Event at 100P/85F - Vessel Pressures
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 84 Figure 7.8 MSIV ATWS Overpressurization Event at 100P/85F - Safety/Relief Valve Flow Rates
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 85 8.0 OPERATING LIMITS AND COLR INPUT 8.1 MCPR Limits The determination of the MCPR limits for Brunswick Unit 1 Cycle 23 is based on the analyses of the limiting anticipated operational occurrences (AOOs). For Brunswick Unit 1 Cycle 23, [
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| ]
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| The MCPR operating limits are established so that less than 0.1% of the fuel rods in the core are expected to experience boiling transition during an AOO initiated from rated or off-rated conditions and are based on a two-loop operation SLMCPR of 1.07 and a single-loop operation SLMCPR of 1.09. Exposure-dependent MCPR limits were established to support operation from BOC to near end of cycle (NEOC), BOC to end-of-cycle licensing basis (EOCLB), and combined FFTR/Coastdown as defined by the core average exposures listed in Table 5.1. MCPR limits are established to support base case operation and the EOOS scenarios presented in Table 1.1.
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| Cycle 23 two-loop operation MCPRp limits for ATRIUM 10XM and ATRIUM 11 fuel are presented in Tables 8.1 - 8.9 for base case operation and the EOOS conditions. Limits are presented for nominal scram speed (NSS), extended scram speed (ESS), and Technical Specification scram speed (TSSS) insertion times for the exposure ranges considered. An assumed RBM high power setpoint of 111% was used to develop the MCPRp limits. Tables 8.1 through 8.3 present the MCPRp limits for the BOC to NEOC exposure range. Tables 8.4 through 8.6 present the MCPRp limits for the BOC to EOCLB exposure range. Tables 8.7 through 8.9 present the MCPRp limits for FFTR/Coastdown operation. The FFTR/Coastdown limits (both base case and TBVOOS) support both nominal and constant rated dome pressure operation
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 86 with feedwater temperatures consistent with a feedwater temperature reduction of up to 110.3°F at rated power. MCPRp limits for single-loop operation are 0.02 higher for all cases.
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| MCPRf limits that protect against fuel failures during a postulated slow flow excursion are presented in Tables 8.10 and 8.11. These MCPRf limits are applicable for all Cycle 23 exposures and the EOOS conditions identified in Table 1.1.
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| 8.2 LHGR Limits The LHGR limits for ATRIUM 11 and ATRIUM 10XM are presented in Table 8.12 (References 6 and 36, respectively). Power- and flow-dependent multipliers (LHGRFACp and LHGRFACf) are applied directly to the LHGR limits to protect against fuel melting and overstraining of the cladding during an AOO for both UO2 and gadolinia bearing rods.
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| The ATRIUM 10XM and ATRIUM 11 LHGRFACp multipliers are determined using the RODEX4 thermal-mechanical methodology (Reference 30) using the AURORA-B transient simulations.
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| For the LHGRFACp evaluations [
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| ]
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| Exposure-dependent ATRIUM 11 and ATRIUM 10XM LHGRFACp multipliers were established to support operation from BOC to EOCLB (Tables 8.13 - 8.15), and combined FFTR/Coastdown (Tables 8.16 - 8.18) for NSS, ESS, and TSSS insertion times, respectively and for the EOOS conditions identified in Table 1.1. The FFTR/Coastdown limits (both base case and TBVOOS) support both nominal and constant rated dome pressure operation with
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 87 feedwater temperatures consistent with a feedwater temperature reduction of up to 110.3°F at rated power.
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| LHGRFACf multipliers are established to provide protection against fuel centerline melt and overstraining of the cladding during a postulated slow flow excursion. For ATRIUM 10XM and ATRIUM 11 fuel, the LHGRFACf multipliers are presented in Table 8.19 and are applicable for all Cycle 23 exposures and the EOOS conditions identified in Table 1.1.
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| 8.3 MAPLHGR Limits The ATRIUM 10XM TLO MAPLHGR limits are presented in Table 8.20. For operation in SLO, a multiplier of 0.80 must be applied to the TLO MAPLHGR limits.
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| The ATRIUM 11 TLO MAPLHGR limits are presented in Table 8.20. For operation in SLO, a multiplier of 0.85 must be applied to the TLO MAPLHGR limits.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 88 Table 8.1 MCPRp Limits for NSS Insertion Times BOC to < NEOC*,
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| EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.36 1.36 90.0 1.41 1.40 50.0 1.72 1.63 Base > 65%F 65%F > 65%F 65%F case 50.0 1.86 1.74 1.87 1.65 operation 26.0 2.23 2.06 2.17 1.98 26.0 2.30 2.24 2.29 2.18 23.0 2.41 2.41 2.30 2.30 100.0 1.37 1.39 90.0 1.41 1.43 50.0 1.72 1.76
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| > 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.86 1.74 1.87 1.66 26.0 2.23 2.06 2.17 2.00 26.0 3.21 3.21 2.95 2.95 23.0 3.28 3.28 2.99 2.99 100.0 1.36 1.36 90.0 1.41 1.40 50.0 1.72 1.67
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| > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.86 1.74 1.87 1.65 26.0 2.23 2.06 2.17 1.98 26.0 2.42 2.31 2.37 2.19 23.0 2.54 2.46 2.45 2.36 100.0 1.40 1.42 90.0 1.43 1.46 50.0 1.72 1.79 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.86 1.74 1.88 1.67 26.0 2.23 2.06 2.22 2.02 26.0 3.24 3.24 3.09 3.09 23.0 3.37 3.37 3.09 3.09
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| * Limits support operation with any combination of 1 SRVOOS, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher. Note that operation in SLO is only supported up to a maximum power level of 71.1% of rated and is not allowed in MELLLA+.
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| Limits are only valid if control rods at a shallow position (i.e. greater than Notch 36) are no further withdrawn than their position specified in Reference 3. If not, the BEO-III acceptance criteria may not be met.
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| Note that FHOOS is not allowed in MELLLA+.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 89 Table 8.2 MCPRp Limits for ESS Insertion Times BOC to < NEOC*,
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| EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.36 1.36 90.0 1.41 1.40 50.0 1.72 1.63 Base > 65%F 65%F > 65%F 65%F case 50.0 1.86 1.74 1.87 1.65 operation 26.0 2.23 2.06 2.17 1.98 26.0 2.30 2.24 2.29 2.18 23.0 2.41 2.41 2.30 2.30 100.0 1.37 1.39 90.0 1.41 1.43 50.0 1.72 1.76
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| > 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.86 1.74 1.87 1.69 26.0 2.23 2.06 2.17 2.00 26.0 3.21 3.21 2.95 2.95 23.0 3.28 3.28 2.99 2.99 100.0 1.36 1.36 90.0 1.41 1.40 50.0 1.72 1.67
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| > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.86 1.74 1.87 1.65 26.0 2.23 2.06 2.17 1.98 26.0 2.42 2.31 2.37 2.19 23.0 2.54 2.46 2.45 2.36 100.0 1.44 1.44 90.0 1.45 1.47 50.0 1.74 1.80 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.88 1.76 1.89 1.72 26.0 2.25 2.08 2.23 2.03 26.0 3.26 3.26 3.10 3.10 23.0 3.39 3.39 3.10 3.10
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| * Limits support operation with any combination of 1 SRVOOS, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher. Note that operation in SLO is only supported up to a maximum power level of 71.1% of rated and is not allowed in MELLLA+.
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| Limits are only valid if control rods at a shallow position (i.e. greater than Notch 36) are no further withdrawn than their position specified in Reference 3. If not, the BEO-III acceptance criteria may not be met.
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| Note that FHOOS is not allowed in MELLLA+.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 90 Table 8.3 MCPRp Limits for TSSS Insertion Times BOC to < NEOC*,
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| EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.46 1.44 90.0 1.47 1.47 50.0 1.75 1.75 Base > 65%F 65%F > 65%F 65%F case 50.0 1.89 1.77 1.89 1.75 operation 26.0 2.26 2.09 2.19 2.00 26.0 2.33 2.27 2.31 2.20 23.0 2.44 2.44 2.32 2.32 100.0 1.52 1.50 90.0 1.53 1.54 50.0 1.78 1.85
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| > 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.92 1.80 1.92 1.86 26.0 2.29 2.12 2.22 2.17 26.0 3.27 3.27 3.00 3.00 23.0 3.34 3.34 3.04 3.04 100.0 1.46 1.44 90.0 1.47 1.47 50.0 1.75 1.76
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| > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.89 1.77 1.89 1.75 26.0 2.26 2.09 2.19 2.00 26.0 2.45 2.34 2.39 2.21 23.0 2.57 2.49 2.47 2.38 100.0 1.52 1.56 90.0 1.56 1.60 50.0 1.80 1.95 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.92 1.80 1.95 1.89 26.0 2.29 2.12 2.47 2.25 26.0 3.30 3.30 3.16 3.16 23.0 3.43 3.43 3.16 3.16
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| * Limits support operation with any combination of 1 SRVOOS, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher. Note that operation in SLO is only supported up to a maximum power level of 71.1% of rated and is not allowed in MELLLA+.
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| Limits are only valid if control rods at a shallow position (i.e. greater than Notch 36) are no further withdrawn than their position specified in Reference 3. If not, the BEO-III acceptance criteria may not be met.
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| Note that FHOOS is not allowed in MELLLA+.
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| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 91 Table 8.4 MCPRp Limits for NSS Insertion Times BOC to < EOCLB*,
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| EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.38 1.38 90.0 1.41 1.40 50.0 1.72 1.63 Base > 65%F 65%F > 65%F 65%F case 50.0 1.86 1.74 1.87 1.66 operation 26.0 2.23 2.06 2.17 1.98 26.0 2.30 2.24 2.29 2.18 23.0 2.41 2.41 2.30 2.30 100.0 1.42 1.44 90.0 1.44 1.47 50.0 1.73 1.78
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| > 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.87 1.75 1.89 1.71 26.0 2.24 2.07 2.19 2.02 26.0 3.22 3.22 2.97 2.97 23.0 3.29 3.29 3.01 3.01 100.0 1.38 1.38 90.0 1.41 1.40 50.0 1.72 1.67
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| > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.86 1.74 1.87 1.66 26.0 2.23 2.06 2.17 1.98 26.0 2.42 2.31 2.37 2.19 23.0 2.54 2.46 2.45 2.36 100.0 1.44 1.46 90.0 1.46 1.48 50.0 1.74 1.81 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.88 1.76 1.90 1.73 26.0 2.25 2.08 2.24 2.04 26.0 3.26 3.26 3.11 3.11 23.0 3.39 3.39 3.11 3.11
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| * Limits support operation with any combination of 1 SRVOOS, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher. Note that operation in SLO is only supported up to a maximum power level of 71.1% of rated and is not allowed in MELLLA+.
| |
| | |
| Limits are only valid if control rods at a shallow position (i.e. greater than Notch 36) are no further withdrawn than their position specified in Reference 3. If not, the BEO-III acceptance criteria may not be met.
| |
| | |
| Note that FHOOS is not allowed in MELLLA+.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 92 Table 8.5 MCPRp Limits for ESS Insertion Times BOC to < EOCLB*,
| |
| EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.38 1.39 90.0 1.41 1.40 50.0 1.72 1.63 Base > 65%F 65%F > 65%F 65%F case 50.0 1.86 1.74 1.87 1.66 operation 26.0 2.23 2.06 2.17 1.98 26.0 2.30 2.24 2.29 2.18 23.0 2.41 2.41 2.30 2.30 100.0 1.44 1.46 90.0 1.45 1.48 50.0 1.74 1.79
| |
| > 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.88 1.76 1.90 1.72 26.0 2.25 2.08 2.20 2.03 26.0 3.23 3.23 2.98 2.98 23.0 3.30 3.30 3.02 3.02 100.0 1.38 1.39 90.0 1.41 1.40 50.0 1.72 1.67
| |
| > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.86 1.74 1.87 1.66 26.0 2.23 2.06 2.17 1.98 26.0 2.42 2.31 2.37 2.19 23.0 2.54 2.46 2.45 2.36 100.0 1.44 1.48 90.0 1.46 1.49 50.0 1.74 1.82 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.88 1.76 1.91 1.74 26.0 2.25 2.08 2.25 2.05 26.0 3.26 3.26 3.12 3.12 23.0 3.39 3.39 3.12 3.12
| |
| * Limits support operation with any combination of 1 SRVOOS, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher. Note that operation in SLO is only supported up to a maximum power level of 71.1% of rated and is not allowed in MELLLA+.
| |
| | |
| Limits are only valid if control rods at a shallow position (i.e. greater than Notch 36) are no further withdrawn than their position specified in Reference 3. If not, the BEO-III acceptance criteria may not be met.
| |
| | |
| Note that FHOOS is not allowed in MELLLA+.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 93 Table 8.6 MCPRp Limits for TSSS Insertion Times BOC to < EOCLB*,
| |
| EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.54 1.56 90.0 1.54 1.56 50.0 1.79 1.81 Base > 65%F 65%F > 65%F 65%F case 50.0 1.93 1.81 1.95 1.81 operation 26.0 2.30 2.13 2.25 2.06 26.0 2.37 2.31 2.37 2.26 23.0 2.48 2.48 2.38 2.38 100.0 1.58 1.62 90.0 1.58 1.62 50.0 1.81 1.93
| |
| > 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.95 1.83 1.98 1.92 26.0 2.32 2.15 2.28 2.23 26.0 3.30 3.30 3.06 3.06 23.0 3.37 3.37 3.10 3.10 100.0 1.54 1.56 90.0 1.54 1.56 50.0 1.79 1.82
| |
| > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.93 1.81 1.95 1.81 26.0 2.30 2.13 2.25 2.06 26.0 2.49 2.38 2.45 2.27 23.0 2.61 2.53 2.53 2.44 100.0 1.58 1.62 90.0 1.59 1.63 50.0 1.83 1.98 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS 50.0 1.95 1.83 1.98 1.92 26.0 2.32 2.15 2.50 2.28 26.0 3.33 3.33 3.19 3.19 23.0 3.46 3.46 3.19 3.19
| |
| * Limits support operation with any combination of 1 SRVOOS, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher. Note that operation in SLO is only supported up to a maximum power level of 71.1% of rated and is not allowed in MELLLA+.
| |
| | |
| Limits are only valid if control rods at a shallow position (i.e. greater than Notch 36) are no further withdrawn than their position specified in Reference 3. If not, the BEO-III acceptance criteria may not be met.
| |
| | |
| Note that FHOOS is not allowed in MELLLA+.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 94 Table 8.7 MCPRp Limits for NSS Insertion Times FFTR/Coastdown*,,
| |
| EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.38 1.38 90.0 1.41 1.40 50.0 1.72 1.67 Base > 65%F 65%F > 65%F 65%F case 50.0 1.86 1.74 1.87 1.66 operation 26.0 2.23 2.06 2.17 1.98 26.0 2.42 2.31 2.37 2.19 23.0 2.54 2.46 2.45 2.36 100.0 1.46 1.46 90.0 1.47 1.48 50.0 1.75 1.81
| |
| > 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.89 1.77 1.90 1.73 26.0 2.26 2.09 2.24 2.04 26.0 3.27 3.27 3.11 3.11 23.0 3.40 3.40 3.11 3.11
| |
| * Limits support operation with any combination of 1 SRVOOS, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher. Note that operation in SLO is only supported up to a maximum power level of 71.1% of rated and is not allowed in MELLLA+.
| |
| | |
| Limits are only valid if control rods at a shallow position (i.e. greater than Notch 36) are no further withdrawn than their position specified in Reference 3. If not, the BEO-III acceptance criteria may not be met.
| |
| | |
| Note that reduced feedwater temperatures such as FFTR are not allowed in MELLLA+; however, the FFTR/Coastdown limits may be conservatively applied to operation in the MELLLA+ domain at these exposures.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 95 Table 8.8 MCPRp Limits for ESS Insertion Times FFTR/Coastdown*,,
| |
| EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.39 1.39 90.0 1.41 1.40 50.0 1.72 1.67 Base > 65%F 65%F > 65%F 65%F case 50.0 1.86 1.74 1.87 1.66 operation 26.0 2.23 2.06 2.17 1.98 26.0 2.42 2.31 2.37 2.19 23.0 2.54 2.46 2.45 2.36 100.0 1.46 1.48 90.0 1.47 1.49 50.0 1.75 1.82
| |
| > 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.89 1.77 1.91 1.74 26.0 2.26 2.09 2.25 2.05 26.0 3.27 3.27 3.12 3.12 23.0 3.40 3.40 3.12 3.12
| |
| * Limits support operation with any combination of 1 SRVOOS, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher. Note that operation in SLO is only supported up to a maximum power level of 71.1% of rated and is not allowed in MELLLA+.
| |
| | |
| Limits are only valid if control rods at a shallow position (i.e. greater than Notch 36) are no further withdrawn than their position specified in Reference 3. If not, the BEO-III acceptance criteria may not be met.
| |
| | |
| Note that reduced feedwater temperatures such as FFTR are not allowed in MELLLA+; however, the FFTR/Coastdown limits may be conservatively applied to operation in the MELLLA+ domain at these exposures.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 96 Table 8.9 MCPRp Limits for TSSS Insertion Times FFTR/Coastdown*,,
| |
| EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) MCPRp MCPRp 100.0 1.60 1.62 90.0 1.60 1.62 50.0 1.82 1.85 Base > 65%F 65%F > 65%F 65%F case 50.0 1.96 1.84 1.98 1.84 operation 26.0 2.33 2.16 2.28 2.09 26.0 2.52 2.41 2.48 2.30 23.0 2.64 2.56 2.56 2.47 100.0 1.66 1.68 90.0 1.66 1.68 50.0 1.87 2.01
| |
| > 65%F 65%F > 65%F 65%F TBVOOS 50.0 1.99 1.87 2.01 1.95 26.0 2.36 2.19 2.53 2.31 26.0 3.37 3.37 3.22 3.22 23.0 3.50 3.50 3.22 3.22
| |
| * Limits support operation with any combination of 1 SRVOOS, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher. Note that operation in SLO is only supported up to a maximum power level of 71.1% of rated and is not allowed in MELLLA+.
| |
| | |
| Limits are only valid if control rods at a shallow position (i.e. greater than Notch 36) are no further withdrawn than their position specified in Reference 3. If not, the BEO-III acceptance criteria may not be met.
| |
| | |
| Note that reduced feedwater temperatures such as FFTR are not allowed in MELLLA+; however, the FFTR/Coastdown limits may be conservatively applied to operation in the MELLLA+ domain at these exposures.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 97 Table 8.10 Flow-Dependent MCPR Limits ATRIUM 10XM Fuel*
| |
| Core Flow MCPRf MCPRf
| |
| (% of rated) MSIVIS MSIVOOS 0.0 1.48 1.66 31.0 1.48 1.66 60.0 1.42 1.50 75.0 1.30 --
| |
| 81.0 -- 1.30 107.0 1.30 1.30 Table 8.11 Flow-Dependent MCPR Limits ATRIUM 11 Fuel*
| |
| Core Flow MCPRf MCPRf
| |
| (% of rated) MSIVIS MSIVOOS 0.0 1.42 1.57 31.0 1.42 1.57 60.0 1.30 --
| |
| 77.0 -- 1.30 107.0 1.30 1.30
| |
| * Limits are only valid if control rods at a shallow position (i.e. greater than Notch 36) are no further withdrawn than their position specified in Reference 3. If not, the BEO-III acceptance criteria may not be met.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 98 Table 8.12 Steady-State LHGR Limits Peak ATRIUM 10XM Peak ATRIUM 11 Pellet Exposure LHGR Pellet Exposure LHGR (GWd/MTU) (kW/ft) (GWd/MTU) (kW/ft) 0.0 15.1 0.0 13.6 6.0 14.1 --* --
| |
| 18.9 14.1 21.0 13.6 54.0 10.6 53.0 10.2 74.4 5.4 80.0 3.5
| |
| * -- indicates that the ATRIUM 11 limit does not include any breakpoint at this exposure.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 99 Table 8.13 LHGRFACp Multipliers for NSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) LHGRFACp LHGRFACp 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.96 Base > 65%F 65%F > 65%F 65%F case 50.0 0.92 1.00 0.85 0.93 operation 26.0 0.75 0.86 0.67 0.79 26.0 0.49 0.51 0.45 0.48 23.0 0.49 0.51 0.45 0.48 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.92
| |
| > 65%F 65%F > 65%F 65%F TBVOOS 0.92 1.00 0.85 0.93 50.0 26.0 0.75 0.86 0.67 0.79 26.0 0.45 0.51 0.41 0.48 23.0 0.41 0.50 0.37 0.45 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.90
| |
| > 65%F 65%F > 65%F 65%F FHOOS*
| |
| 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.47 0.49 0.43 0.46 23.0 0.46 0.49 0.42 0.45 100.0 1.00 0.98 90.0 1.00 0.97 50.0 0.96 0.87 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS* 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.42 0.49 0.37 0.46 23.0 0.38 0.47 0.34 0.42
| |
| * Note that FHOOS is not allowed in MELLLA+.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 100 Table 8.14 LHGRFACp Multipliers for ESS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) LHGRFACp LHGRFACp 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.96 Base > 65%F 65%F > 65%F 65%F case 50.0 0.92 1.00 0.85 0.93 operation 26.0 0.75 0.86 0.67 0.79 26.0 0.49 0.51 0.45 0.48 23.0 0.49 0.51 0.45 0.48 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.92
| |
| > 65%F 65%F > 65%F 65%F TBVOOS 0.92 1.00 0.85 0.93 50.0 26.0 0.75 0.86 0.67 0.79 26.0 0.45 0.51 0.41 0.48 23.0 0.41 0.50 0.37 0.45 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.90
| |
| > 65%F 65%F > 65%F 65%F FHOOS*
| |
| 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.47 0.49 0.43 0.46 23.0 0.46 0.49 0.42 0.45 100.0 1.00 0.97 90.0 1.00 0.97 50.0 0.96 0.87 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS* 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.42 0.49 0.37 0.46 23.0 0.38 0.47 0.34 0.42
| |
| * Note that FHOOS is not allowed in MELLLA+.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 101 Table 8.15 LHGRFACp Multipliers for TSSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) LHGRFACp LHGRFACp 100.0 1.00 1.00 90.0 1.00 -
| |
| 50.0 1.00 0.93 Base > 65%F 65%F > 65%F 65%F case 50.0 0.92 1.00 0.85 0.93 operation 26.0 0.75 0.86 0.67 0.79 26.0 0.49 0.51 0.45 0.48 23.0 0.49 0.51 0.45 0.48 100.0 1.00 0.99 90.0 1.00 -
| |
| 50.0 0.95 0.85
| |
| > 65%F 65%F > 65%F 65%F TBVOOS 0.92 1.00 0.85 0.93 50.0 26.0 0.75 0.86 0.67 0.79 26.0 0.45 0.51 0.41 0.48 23.0 0.41 0.50 0.37 0.45 100.0 1.00 0.96 90.0 1.00 -
| |
| 50.0 0.96 0.88
| |
| > 65%F 65%F > 65%F 65%F FHOOS*
| |
| 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.47 0.49 0.43 0.46 23.0 0.46 0.49 0.42 0.45 100.0 1.00 0.94 90.0 1.00 -
| |
| 50.0 0.90 0.82 TBVOOS > 65%F 65%F > 65%F 65%F FHOOS* 50.0 0.90 1.00 0.82 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.42 0.49 0.37 0.46 23.0 0.38 0.47 0.34 0.42
| |
| * Note that FHOOS is not allowed in MELLLA+.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 102 Table 8.16 LHGRFACp Multipliers for NSS Insertion Times FFTR/Coastdown*
| |
| EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) LHGRFACp LHGRFACp 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.90 Base > 65%F 65%F > 65%F 65%F case 50.0 0.92 1.00 0.85 0.93 operation 26.0 0.75 0.86 0.67 0.79 26.0 0.47 0.49 0.43 0.46 23.0 0.46 0.49 0.42 0.45 100.0 1.00 0.98 90.0 1.00 0.97 50.0 0.96 0.87
| |
| > 65%F 65%F > 65%F 65%F TBVOOS 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.42 0.49 0.37 0.46 23.0 0.38 0.47 0.34 0.42
| |
| * Note that reduced feedwater temperatures such as FFTR are not allowed in MELLLA+; however, the FFTR/Coastdown limits may be conservatively applied to operation in the MELLLA+ domain at these exposures.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 103 Table 8.17 LHGRFACp Multipliers for ESS Insertion Times FFTR/Coastdown*
| |
| EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) LHGRFACp LHGRFACp 100.0 1.00 1.00 90.0 1.00 1.00 50.0 1.00 0.90 Base > 65%F 65%F > 65%F 65%F case 50.0 0.92 1.00 0.85 0.93 operation 26.0 0.75 0.86 0.67 0.79 26.0 0.47 0.49 0.43 0.46 23.0 0.46 0.49 0.42 0.45 100.0 1.00 0.97 90.0 1.00 0.97 50.0 0.96 0.87
| |
| > 65%F 65%F > 65%F 65%F TBVOOS 50.0 0.92 1.00 0.85 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.42 0.49 0.37 0.46 23.0 0.38 0.47 0.34 0.42
| |
| * Note that reduced feedwater temperatures such as FFTR are not allowed in MELLLA+; however, the FFTR/Coastdown limits may be conservatively applied to operation in the MELLLA+ domain at these exposures.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 104 Table 8.18 LHGRFACp Multipliers for TSSS Insertion Times FFTR/Coastdown*
| |
| EOOS Power ATRIUM 10XM ATRIUM 11 Condition (% rated) LHGRFACp LHGRFACp 100.0 1.00 0.96 90.0 1.00 -
| |
| 50.0 0.96 0.88 Base > 65%F 65%F > 65%F 65%F case 50.0 0.92 1.00 0.85 0.93 operation 26.0 0.75 0.86 0.67 0.79 26.0 0.47 0.49 0.43 0.46 23.0 0.46 0.49 0.42 0.45 100.0 1.00 0.94 90.0 1.00 -
| |
| 50.0 0.90 0.82
| |
| > 65%F 65%F > 65%F 65%F TBVOOS 50.0 0.90 1.00 0.82 0.93 26.0 0.75 0.86 0.67 0.79 26.0 0.42 0.49 0.37 0.46 23.0 0.38 0.47 0.34 0.42
| |
| * Note that reduced feedwater temperatures such as FFTR are not allowed in MELLLA+; however, the FFTR/Coastdown limits may be conservatively applied to operation in the MELLLA+ domain at these exposures.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 105 Table 8.19 ATRIUM 10XM and ATRIUM 11 LHGRFACf Multipliers All Cycle 23 Exposures Core Flow
| |
| (% of rated) LHGRFACf 0.0 0.52 31.0 0.52 75.0 1.00 107.0 1.00 Table 8.20 Framatome Fuel MAPLHGR Limits Average Planar ATRIUM 10XM Average Planar ATRIUM 11 Exposure MAPLHGR Exposure MAPLHGR (GWd/MTU) (kW/ft) (GWd/MTU) (kW/ft) 0.0 13.1 0.0 12.0 15.0 13.1 20.0 12.0 67.0 7.7 60.0 9.0
| |
| -- -- 69.0 7.2
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 106 Figure 8.1 [
| |
| ]
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 107 Figure 8.2 [
| |
| ]
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 108
| |
| | |
| ==9.0 REFERENCES==
| |
| : 1. ANP-3705P Revision 1, Applicability of Framatome BWR Methods to Brunswick with ATRIUM 11 Fuel, Framatome Inc., November 2018.
| |
| : 2. NEDO-33006-A Revision 3, General Electric Boiling Water Reactor Maximum Extended Load Line Limit Analysis Plus, General Electric Hitachi Nuclear Energy America, LLC, June 2009. (available in ADAMS Accession Number ML091800530)
| |
| : 3. ANP-3759P Revision 2, Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report, Framatome, October 2019.
| |
| : 4. FS1-0043234 Revision 2.0, Brunswick Unit 1 Cycle 23 Calculation Plan, Framatome Inc., July 2019.
| |
| : 5. ANP-2948(P) Revision 2, Mechanical Design Report for Brunswick ATRIUM 10XM Fuel Assemblies, AREVA, January 2017.
| |
| : 6. ANP-3791P Revision 0, ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23, Framatome Inc., October 2019.
| |
| : 7. ANP-3686P Revision 0, Mechanical Design Report for Brunswick ATRIUM 11 Fuel Assemblies, Framatome, September 2018.
| |
| : 8. Duke Energy letter to NRC dated October 11, 2018, Request for License Amendment Regarding Application of Advanced Framatome Methodologies (ADAMS Accession Number ML18284A395).
| |
| : 9. ANP-3643P Revision 0, Brunswick Unit 1 Thermal-Hydraulic Design Report for ATRIUM 11 Fuel Assemblies, Framatome, August 2018.
| |
| : 10. ANP-10307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011.
| |
| : 11. ANP-10298P-A Revision 1, ACE/ATRIUM 10XM Critical Power Correlation, AREVA Inc.,
| |
| March 2014.
| |
| : 12. ANP-10335P-A Revision 0, ACE/ATRIUM 11 Critical Power Correlation, Framatome, May 2018.
| |
| : 13. XN-NF-80-19(P)(A) Volume 1 and Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.
| |
| : 14. XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.
| |
| : 15. EMF-CC-074(P)(A) Volume 4 Revision 0, BWR Stability Analysis - Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.
| |
| : 16. DPC-NE-1009 Revision 0, Brunswick Nuclear Plant Implementation of Best-estimate Enhanced Option III, Duke Energy, September 2018. (available in ADAMS Accession Number ML18284A395)
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 109
| |
| : 17. ANP-3703P Revision 0, BEO-III Analysis Methodology for Brunswick Using RAMONA5-FA, Framatome, August 2018.
| |
| : 18. DUKE-0B21-1104-000(NP), Safety Analysis Report for Brunswick Steam Electric Plant Units 1 and 2 Maximum Extended Load Line Limit Analysis Plus, July 2016. (available in ADAMS Accession Number ML16257A411)
| |
| : 19. ANP-10300P-A Revision 1, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios, Framatome Inc., January 2018.
| |
| : 20. XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.
| |
| : 21. 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.
| |
| : 22. Operating License and Technical Specifications, Brunswick Steam Electric Plant, Unit No 1, Duke Energy, as amended.
| |
| : 23. ANF-1358(P)(A) Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Framatome ANP, September 2005.
| |
| : 24. ANP-3105P Revision 1, Brunswick Units 1 and 2 LOCA Break Spectrum Analysis for ATRIUM 10XM Fuel for MELLLA+ Operation, AREVA, July 2015.
| |
| : 25. ANP-3106P Revision 2, Brunswick Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM 10XM Fuel for MELLLA+ Operation, AREVA, December 2015.
| |
| : 26. ANP-3674P Revision 2, Brunswick Units 1 and 2 LOCA Analysis for ATRIUM 11 Fuel, Framatome, May 2019.
| |
| : 27. FS1-0040060 Revision 1.0, 10 CFR 50.46 PCT Error Report for Brunswick Units 1 and 2 for MELLLA+ Operation, Framatome Inc., December 2018.
| |
| : 28. ANP-3672(P) Revision 0, Brunswick Nuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUM' 11 Fuel, Framatome, August 2018.
| |
| : 29. ANP-3671 (P) Revision 0, Brunswick Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for ATRIUM' 11 Fuel, Framatome, December 2018.
| |
| : 30. BAW-10247PA Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP, February 2008.
| |
| : 31. ANP-3694P Revision 0, ATWS-I Analysis Methodology for Brunswick Using RAMONA5-FA, June 2018.
| |
| : 32. ANP-10333P-A Revision 0, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA), Framatome, March 2018.
| |
| : 33. ANP-3714P Revision 0, Brunswick ATRIUM 11 Control Rod Drop Accident Analyses with the AURORA-B CRDA Methodology, September 2018.
| |
| | |
| Controlled Document Framatome Inc ANP-3808NP Brunswick Unit 1 Cycle 23 Revision 0 Reload Safety Analysis Page 110
| |
| : 34. DG-1327, Pressurized Water Reactor Control Rod Ejection and Boiling Water Reactor Control Rod Drop Accidents, US NRC, November 2016. (available in ADAMS Accession Number ML16124A200)
| |
| : 35. FS1-0038655 Revision 1.0, Transmittal of BNP Calculation 0B21-1281 Revision 5 (NF18-049) DBA Radiological Core Inventory Fuel Design Applicability, June 2018.
| |
| : 36. ANP-3804P Revision 0, ATRIUM 10XM Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23, Framatome Inc., October 2019.
| |
| : 37. NRC E-mail Capture, Request for Additional Information - Brunswick ATRIUM 11 LAR, ADAMS (available in ADAMS Accession Number ML19283C829), October 9, 2019.
| |
| | |
| RA-19-0411 Enclosure 4 ANP-3791NP, ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23, Revision 0
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| | |
| Controlled Document ATRIUM 11 Fuel Rod Thermal- ANP-3791NP Revision 0 Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report October 2019 (c) 2019 Framatome Inc.
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| | |
| Controlled Document ANP-3791NP Revision 0 Copyright © 2019 Framatome Inc.
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| All Rights Reserved FUELGUARD and ATRIUM is a trademark or registered trademark of Framatome or its affiliates, in the USA or other countries.
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| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page i Nature of Changes Section(s)
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| Item or Page(s) Description and Justification 1 All Initial Issue
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| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page ii Contents Page
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| | |
| ==1.0 INTRODUCTION==
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| ............................................................................................... 1-1 2.0
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| | |
| ==SUMMARY==
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| AND CONCLUSIONS .................................................................... 2-1 3.0 FUEL ROD DESIGN EVALUATION .................................................................. 3-1 3.1 Fuel Rod Design ..................................................................................... 3-1 3.2 RODEX4 and Statistical Methodology Summary .................................... 3-2 3.3 Summary of Fuel Rod Design Evaluation ............................................... 3-4 3.3.1 Internal Hydriding ......................................................................... 3-6 3.3.2 Cladding Collapse ........................................................................ 3-6 3.3.3 Overheating of Fuel Pellets .......................................................... 3-6 3.3.4 Stress and Strain Limits ............................................................... 3-7 3.3.5 Fuel Densification and Swelling ................................................... 3-8 3.3.6 Fatigue ......................................................................................... 3-8 3.3.7 Oxidation, Hydriding, and Crud Buildup ....................................... 3-9 3.3.8 Rod Internal Pressure ................................................................ 3-10 3.3.9 Plenum Spring Design (Fuel Assembly Handling)...................... 3-10
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| | |
| ==4.0 REFERENCES==
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| .................................................................................................. 4-1
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| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page iii List of Tables Table 2-1 Summary of Fuel Rod Design Evaluation Results (MELLLA+) ................... 2-2 Table 3-1 Key Fuel Rod Design Parameters, ATRIUM 11 for BRK1-23.................... 3-11 Table 3-2 RODEX4 Fuel Rod Results Equilibrium CycleMELLLA+ ....................... 3-13 Table 3-3 RODEX4 Fuel Rod Results for ATRIUM 11 BRK1-23 Cycle MELLLA+................................................................................................. 3-14 Table 3-4 Cladding and Cladding-End Cap Steady-State Stresses ........................... 3-15 List of Figures Figure 2-1 LHGR Limit (Normal Operation) .................................................................. 2-3
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| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page iv Nomenclature Acronym Definition 3GFG 3rd generation FUELGUARD AOO anticipated operational occurrences ASME American Society of Mechanical Engineers B&PV Boiler and Pressure Vessel BOL beginning of life BWR boiling water reactor CRWE control rod withdrawal error CUF cumulative usage factor EOL end of life FDL fuel design limit ID inside diameter LAR License Amendment Request LHGR linear heat generation rate LTP lower tie plate MWd/kgU megawatt days per kilogram of initial uranium MELLLA+ maximum extended load line limit analysis plus NRC Nuclear Regulatory Commission, U. S.
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| OD outside diameter PCI pellet-to-cladding-interaction PLFR part length fuel rod ppm parts per million SRA stress relieved annealed S-N stress amplitude versus number of cycles UTL upper tolerance limit
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| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 1-1
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| ==1.0 INTRODUCTION==
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| | |
| Results of the fuel rod thermal-mechanical analyses are presented to demonstrate that the applicable design criteria are satisfied. The analyses are for the Framatome Inc. ATRIUM 11 fuel that will be inserted for operation in Brunswick Unit 1 Cycle 23 as reload batch BRK1-23.
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| These analyses assume the use of chromia additive in the enriched and natural urania portions of the fuel and assume operation in the Maximum Extended Load Line Limit Plus (MELLLA+)
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| operation domain. Both the design criteria and the analysis methodology have been approved by the U. S. NRC (NRC).
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| The analysis results are evaluated according to the generic fuel rod thermal and mechanical design criteria contained in ANF-89-98(P)(A) Revision 1 and Supplement 1 (Reference 1) along with design criteria provided in the RODEX4 fuel rod thermal-mechanical topical report (Reference 2)*. Approved methodology for the inclusion of chromia additive in the fuel pellets is also used (Reference 3).
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| The RODEX4 fuel rod thermal-mechanical analysis code is used to analyze the fuel rod for fuel centerline temperature, cladding strain, rod internal pressure, cladding collapse, cladding fatigue and external oxidation. The code and application methodology are described in the RODEX4 topical report (Reference 2). The cladding steady-state stress and plenum spring design methodology are summarized in Reference 1.
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| The following sections describe the fuel rod design, design criteria and methodology with reference to the source topical reports. Results from the analyses are summarized for comparison to the design criteria.
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| * (N.B., the cladding external oxidation limit from that topical report of [ ] was reduced to
| |
| [ ] when the RODEX4 methodology was approved for application to the Brunswick units (Reference 4)).
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| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 2-1 2.0
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| | |
| ==SUMMARY==
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| AND CONCLUSIONS Key results are compared against each design criterion in:
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| - Table 2-1 for MELLLA+ operating domain Results are presented for the limiting cases. Additional RODEX4 results are given in Section 3.0.
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| The analyses support a maximum fuel rod discharge exposure of 62 MWd/kgU.
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| Fuel rod criteria applicable to the design are summarized in Section 3.0. Analyses show the criteria are satisfied when the fuel is operated at or below the LHGR (linear heat generation rate) limit (Fuel Design Limit - FDL) presented in Figure 2-1.
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| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 2-2 Table 2-1 Summary of Fuel Rod Design Evaluation Results (MELLLA+)
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| Criteria Description Criteria Result, Margin or Comment Section*
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| 3.2 Fuel Rod Criteria 3.2.1 Internal hydriding [
| |
| ]
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| (3.1.1) Cladding collapse [ ]
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| (3.1.2) Overheating of fuel No fuel melting [ ]
| |
| pellets margin to fuel melt > 0, °C 3.2.5 Stress and strain limits (3.1.1) Pellet-cladding [ ]
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| (3.1.2) interaction 3.2.5.2 Cladding steady-state [
| |
| stresses
| |
| ]
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| 3.3 Fuel System Criteria (3.1.1) Fatigue [ ]
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| (3.1.1) Oxidation, hydriding, [ ]
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| and crud buildup (3.1.1) Rod internal pressure [ ]
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| (3.1.2) 3.3.9 Fuel rod plenum spring Plenum spring to [
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| (fuel handling)
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| ]
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| * Numbers in the column refer to paragraph sections in the generic design criteria document, ANF 98(P)(A) Revision 1 and Supplement 1 (Reference 1). A number in parentheses is the paragraph section in the RODEX4 fuel rod topical report (Reference 2).
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| Margin is defined as (limit - result).
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| | |
| The cladding external oxidation limit is restricted to [ ] by Reference 4.
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| Controlled Document Framatomme Inc. ANP-37 791NP Revission 0 ATRIUM 11 Fuel Rod Thermal-Mec T chanical Evalu uation for Bru nswick Unit 1 Cycle 23 Licensing Report Pag ge 2-3
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| [
| |
| ]
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| Figuree 2-1 LHGR Limit (Norm mal Operatiion)
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| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-1 3.0 FUEL ROD DESIGN EVALUATION Summaries of the design criteria and methodology are provided in this section along with analysis results in comparison to criteria. Both the fuel rod criteria and fuel system criteria as directly related to the fuel rod analyses are covered.
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| The fuel rod analyses cover normal operating conditions and AOOs (anticipated operational occurrences). The fuel centerline temperature analysis (overheating of fuel) and cladding strain analysis take into account slow transients at rated operating conditions.
| |
| Other fuel rod-related topics on overheating of cladding, cladding rupture, fuel rod mechanical fracturing, rod bow, axial irradiation growth, cladding embrittlement, violent expulsion of fuel and fuel ballooning are evaluated as part of the respective fuel assembly structural analysis, thermal hydraulic analyses, or LOCA analyses and are reported elsewhere. The evaluation of fast transients and transients at off-rated conditions also are reported separately from this report.
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| 3.1 Fuel Rod Design The ATRIUM 11 fuel rod is conventional in design configuration and very similar to past designs such as the ATRIUM 10XM, ATRIUM-10 and ATRIUM-9 fuel rods.
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| [
| |
| ] plenum spring on the upper end of the fuel column assists in maintaining a compact fuel column during shipment and initial reactor operation.
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| There are two Part-length Fuel Rod (PLFR) designs incorporated in the fuel assembly. The longer is [ ] long, while the shorter is [ ] long. [
| |
| ].
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| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-2
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| [
| |
| ].
| |
| As on previous ATRIUM fuel designs that incorporated the 3rd generation FUELGUARD (3GFG)
| |
| Lower Tie Plate (LTP), the PLFRs have a [
| |
| ].
| |
| Table 3-1 lists the main parameters for the fuel rod and components.
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| 3.2 RODEX4 and Statistical Methodology Summary RODEX4 evaluates the thermal-mechanical response of the fuel rod surrounded by coolant.
| |
| The fuel rod model considers the fuel column, gap region, cladding, gas plena and the fill gas and released fission gases. The fuel rod is divided into axial and radial regions with conditions computed for each region. The operational conditions are controlled by the [
| |
| ].
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| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-3 The heat conduction in the fuel and clad is [
| |
| ].
| |
| Mechanical processes include [
| |
| ].
| |
| As part of the methodology, fuel rod power histories are generated [
| |
| ].
| |
| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-4 Since RODEX4 is a best-estimate code, uncertainties are taken into account by a [
| |
| ]. Uncertainties taken into account in the analysis are summarized as:
| |
| * Power measurement and operational uncertainties - [
| |
| ].
| |
| * Manufacturing uncertainties - [
| |
| ].
| |
| * Model uncertainties - [
| |
| ].
| |
| [
| |
| ].
| |
| 3.3 Summary of Fuel Rod Design Evaluation Results from the analyses are listed in Table 3-2 and Table 3-3. Summaries of the methods and codes used in the evaluation are provided in the following paragraphs. The design criteria are also listed along with references to the sections of the design criteria topical reports (References 1 and 2).
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| The fuel rod thermal and mechanical design criteria are summarized as follows.
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| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-5
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| * Internal Hydriding. The fabrication limit [
| |
| ] to preclude cladding failure caused by internal sources of hydrogen (Section 3.2.1 of Reference 1).
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| * Cladding Collapse. Clad creep collapse shall be prevented. [
| |
| ] (Section 3.1.1 of Reference 2).
| |
| * Overheating of Fuel Pellets. The fuel pellet centerline temperature during anticipated transients shall remain below the melting temperature (Section 3.1.2 of Reference 2).
| |
| * Stress and Strain Limits. [
| |
| ] during normal operation and during anticipated transients (Sections 3.1.1 and 3.1.2 of Reference 2).
| |
| Fuel rod cladding steady-state stresses are restricted to satisfy limits derived from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)
| |
| Code (Section 3.2.5.2 of Reference 1).
| |
| * Cladding Fatigue. The fatigue cumulative usage factor for clad stresses during normal operation and design cyclic maneuvers shall be below [ ] (Section 3.1.1 of Reference 2).
| |
| * Cladding Oxidation, Hydriding and Crud Buildup. Section 3.1.1 of Reference 2 limits the maximum cladding oxidation to less than [ ] to prevent clad corrosion failure. The oxidation limit is further reduced to [
| |
| ] (Reference 4).
| |
| * Rod Internal Pressure. The rod internal pressure is limited [
| |
| ] to ensure that significant outward clad creep does not occur and unfavorable hydride reorientation on cooldown does not occur (Section 3.1.1 of Reference 2).
| |
| * Plenum Spring Design (Fuel Handling). The rod plenum spring must maintain a force against the fuel column stack [ ] (Section 3.3.9 of Reference 1).
| |
| Cladding collapse, overheating of fuel, cladding transient strain, cladding cyclic fatigue, cladding oxidation, and rod pressure are evaluated [ ]. Cladding stress and the plenum spring are evaluated [ ].
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| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-6 3.3.1 Internal Hydriding The absorption of hydrogen by the cladding can result in cladding failure due to reduced ductility and formation of hydride platelets. Careful moisture control during fuel fabrication reduces the potential for hydrogen absorption on the inside of the cladding. The fabrication limit [
| |
| ] is verified by quality control inspection during fuel manufacturing.
| |
| 3.3.2 Cladding Collapse Creep collapse of the cladding and the subsequent potential for fuel failure is avoided in the design by limiting the gap formation due to fuel densification subsequent to pellet-clad contact.
| |
| The size of the axial gaps which may form due to densification following first pellet-clad contact shall be less than [ ].
| |
| The evaluation is performed using the RODEX4 code and methodology. RODEX4 takes into account the [
| |
| ].
| |
| Table 3-2 lists the results for an equilibrium cycle operating in the MELLLA+ operating domain.
| |
| Table 3-3 lists the results for ATRIUM 11 BRK1-23 cycle operating in the MELLLA+ operating domain.
| |
| 3.3.3 Overheating of Fuel Pellets Fuel failure from the overheating of the fuel pellets is not allowed. The centerline temperature of the fuel pellets must remain below melting during normal operation and AOOs. The melting point of the fuel includes adjustments for [ ]. Framatome establishes an LHGR limit to protect against fuel centerline melting during steady-state operation and during AOOs.
| |
| Fuel centerline temperature is evaluated using the RODEX4 code and methodology for both normal operating conditions and AOOs.
| |
| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-7 Table 3-2 lists the results for an equilibrium cycle operating in the MELLLA+ operating domain.
| |
| Table 3-3 lists the results for ATRIUM 11 BRK1-23 cycle operating in the MELLLA+ operating domain.
| |
| 3.3.4 Stress and Strain Limits 3.3.4.1 Pellet/Cladding Interaction Cladding strain caused by transient-induced deformations of the cladding is calculated using the RODEX4 code and methodology. [
| |
| ]. The strain limit is 1%.
| |
| Table 3-2 lists the results for an equilibrium cycle operating in the MELLLA+ operating domain.
| |
| Table 3-3 lists the results for ATRIUM 11 BRK1-23 cycle operating in the MELLLA+ operating domain.
| |
| 3.3.4.2 Cladding Stress Cladding stresses are calculated using solid mechanics elasticity solutions and finite element methods. The stresses are conservatively calculated for the individual loadings and are categorized as follows:
| |
| Category Membrane Bending Primary [
| |
| ]
| |
| Secondary [
| |
| ]
| |
| Stresses are calculated at the cladding outer and inner diameter in the three principal directions for both beginning of life (BOL) and end of life (EOL) conditions. At EOL, the stresses due to mechanical bow and contact stress are decreased due to irradiation relaxation. The separate
| |
| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-8 stress components are then combined, and the stress intensities for each category are compared to their respective limits.
| |
| The cladding-to-end cap weld stresses are evaluated for loadings from differential pressure, differential thermal expansion, rod weight, and plenum spring force.
| |
| The design limits are derived from the ASME (American Society of Mechanical Engineers)
| |
| Boiler and Pressure Vessel (B&PV) Code Section III (Reference 5) and the minimum specified material properties.
| |
| Table 3-4 lists the results in comparison to the limits for Beginning-of-Life (BOL) Hot conditions and End-of-Life (EOL) at both Hot and Cold conditions.
| |
| 3.3.5 Fuel Densification and Swelling Fuel densification and swelling are limited by the design criteria for fuel temperature, cladding strain, cladding collapse, and rod internal pressure criteria. Although there are no explicit criteria for fuel densification and swelling, the effect of these phenomena are included in the RODEX4 code and methodology.
| |
| 3.3.6 Fatigue Fuel rod cladding fatigue is calculated using the RODEX4 code and methodology. [
| |
| ]. The CUF (cumulative usage factor) is summed for each of the axial regions of the fuel rod using Miners rule. The axial region with the highest CUF is used in the subsequent [
| |
| ]. The maximum CUF for the cladding must remain below [ ] to satisfy the design criterion.
| |
| Table 3-2 lists the results for an equilibrium cycle operating in the MELLLA+ operating domain.
| |
| Table 3-3 lists the results for ATRIUM 11 BRK1-23 cycle operating in the MELLLA+ operating domain.
| |
| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-9 3.3.7 Oxidation, Hydriding, and Crud Buildup Cladding external oxidation is calculated using the RODEX4 code and methodology. The corrosion model includes an enhancement factor that is derived from poolside measurement data to obtain a fit of the expected oxide thickness. An uncertainty value for the model enhancement factor also is determined from the data. The model uncertainty is included as part of the [ ].
| |
| [
| |
| ].
| |
| In the event abnormal crud is observed at a plant, a specific analysis is required to address the higher crud level. An abnormal level of crud is defined by a formation that increases the calculated fuel average temperature by 25°C above the design basis calculation. The formation of crud is not calculated within RODEX4. Instead, an upper bound of expected crud based on plant observations is input by the use of the crud heat transfer coefficient. The corrosion model also takes into consideration the effect of the higher thermal resistance from the crud on the corrosion rate. A higher corrosion rate is therefore included as part of the abnormal crud evaluation. A similar specific analysis is required if an abnormal corrosion layer is observed instead of crud.
| |
| In the case of the Brunswick units, no additional crud is taken into account in the calculations because an abnormal crud or corrosion layer (beyond the design basis) has not been observed at the Brunswick units.
| |
| [
| |
| ].
| |
| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-10 Currently, [
| |
| ].
| |
| The oxide limit is evaluated such that greater than [
| |
| ].
| |
| Table 3-2 lists the results for an equilibrium cycle operating in the MELLLA+ operating domain.
| |
| Table 3-3 lists the results for ATRIUM 11 BRK1-23 cycle operating in the MELLLA+ operating domain.
| |
| 3.3.8 Rod Internal Pressure Fuel rod internal pressure is calculated using the RODEX4 code and methodology. The maximum rod pressure is calculated under steady-state conditions and also takes into account slow transients. Rod internal pressure is limited to [
| |
| ]. The expected upper bound of rod pressure [
| |
| ] is calculated for comparison to the limit.
| |
| Table 3-2 lists the results for an equilibrium cycle operating in the MELLLA+ operating domain.
| |
| Table 3-3 lists the results for ATRIUM 11 BRK1-23 cycle operating in the MELLLA+ operating domain.
| |
| 3.3.9 Plenum Spring Design (Fuel Assembly Handling)
| |
| The plenum spring must maintain a force against the fuel column to prevent [
| |
| ]. This is accomplished by designing and verifying the spring force in relation to the fuel column weight. The plenum spring is designed such that the [
| |
| ].
| |
| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-11 Table 3-1 Key Fuel Rod Design Parameters, ATRIUM 11 for BRK1-23
| |
| [
| |
| ]
| |
| * The theoretical density of enriched and naturally enriched UO2-Cr pellets is 10.94 g/cm3 while that for UO2-Gd2O3 pellets is 10.96 g/cm3.
| |
| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-12 Table 3-1 Key Fuel Rod Design Parameters, ATRIUM 11 for BRK1-23 (contd)
| |
| [
| |
| ]
| |
| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-13 Table 3-2 RODEX4 Fuel Rod Results Equilibrium CycleMELLLA+*
| |
| [
| |
| ]
| |
| * Note that the results are provided up to fuel assembly discharge.
| |
| Margin is defined as (limit - result).
| |
| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-14 Table 3-3 RODEX4 Fuel Rod Results for ATRIUM 11 BRK1-23 Cycle MELLLA+*
| |
| [
| |
| ]
| |
| * Note that the results are provided up to fuel assembly discharge.
| |
| Margin is defined as (limit - result).
| |
| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 3-15 Table 3-4 Cladding and Cladding-End Cap Steady-State Stresses Result Description, Stress Category Criteria BOL BOL EOL Cold Hot Hot Cladding stress Pm (primary membrane stress) [ ]
| |
| Pm + Pb (primary membrane + [ ]
| |
| bending)
| |
| P + Q (primary + secondary) [ ]
| |
| Cladding-End Cap stress Pm + Pb [ ]
| |
| | |
| Controlled Document Framatome Inc. ANP-3791NP Revision 0 ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23 Licensing Report Page 4-1
| |
| | |
| ==4.0 REFERENCES==
| |
| : 1. ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
| |
| : 2. BAW-10247PA Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP Inc., February 2008.
| |
| : 3. ANP-10340P-A Revision 0. Incorporation of Chromia-Doped Fuel Properties in AREVA Approved Methods, Framatome Inc., May 2018.
| |
| : 4. Letter from Farideh E. Saba (NRC) to Michael J. Annacone (CP&L), BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING ADDITION OF ANALYTICAL METHODOLOGY TOPICAL REPORT TO TECHNICAL SPECIFICATION 5.6.5 (TAC NOS. ME3858 AND ME3859),
| |
| ML11101A043, NRC 1109968, dated April 8, 2011.
| |
| : 5. ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plant Components, 1977.
| |
| : 6. ODonnell, W.J., and B. F. Langer, Fatigue Design Basis for Zircaloy Components, Nuclear Science and Engineering, Vol. 20, 1964.
| |
| | |
| RA-19-0411 Enclosure 6 ANP-3759NP, Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report, Revision 2
| |
| | |
| Controlled Document 0414-12-F04 (Rev. 003, 09/17/2018)
| |
| Brunswick Unit 1 Cycle 23 ANP-3759NP Revision 2 Fuel Cycle Design Report October 2019
| |
| © 2019 Framatome Inc.
| |
| | |
| Controlled Document ANP-3759NP Revision 2 Copyright © 2019 Framatome Inc.
| |
| All Rights Reserved ATRIUM is a trademark or registered trademark of Framatome or its affiliates, in the USA or other countries.
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page i Nature of Changes Section(s) or Item Page(s) Description and Justification 1 All Signification modifications made throughout the document because of core redesign.
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| 2 Section 2.0 Footnote added 3 Table 3.4 Negative hot excess reactivity values were removed.
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| 4 Figure 3.1 Assembly placement error was corrected 5 Figure A.44 Erroneous Figure was replaced 6 Figures 3.4, Less significant corrections were made A.42, A.45, A.53, A.55, A.65, &
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| B.1
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page ii Contents Page
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| ==1.0 INTRODUCTION==
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| ..........................................................................................................1-1 2.0
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| ==SUMMARY==
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| ...................................................................................................................2-1 3.0 CYCLE 23 FUEL CYCLE DESIGN ..............................................................................3-1 3.1 General Description ..........................................................................................3-1 3.2 Control Rod Patterns and Thermal Limits .........................................................3-1 3.3 Hot Excess Reactivity and Cold Shutdown Margin ............................................3-2
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| ==4.0 REFERENCES==
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| .............................................................................................................4-1 Appendix A Brunswick Unit 1 Cycle 23 Step-through Depletion Summary, Control Rod Patterns and Core Average Axial Power and Exposure Distributions ............................................................................... A-1 Appendix B Elevation Views of the Brunswick Unit 1 Cycle 23 Fresh Reload Batch Fuel Assemblies................................................................... B-1 Appendix C Brunswick Unit 1 Cycle 23 Fresh Fuel Locations ........................................ C-1 Appendix D Brunswick Unit 1 Cycle 23 Radial Exposure and Power Distributions ............................................................................................... D-1
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page iii List of Tables Table 2.1 Brunswick Unit 1 Cycle 23 Energy and Key Results Summary ............................2-2 Table 2.2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Assembly ID Range by Nuclear Fuel Type ...............................................................................................2-3 Table 2.3 Assumed ATRIUM 11 MCPR Operating Limit ......................................................2-3 Table 2.4 Assumed ATRIUM 11 LHGR Limit ......................................................................2-4 Table 2.5 Assumed ATRIUM 11 APLHGR Limit ..................................................................2-4 Table 3.1 Cycle 23 Core Composition and Design Parameters ...........................................3-3 Table 3.2 Brunswick Unit 1 Cycle 23 Hot Operating Target k-eff Versus Cycle Exposure .............................................................................................................3-4 Table 3.3 Brunswick Unit 1 Cycle 23 Cold Critical Target k-eff Versus Cycle Exposure .......3-4 Table 3.4 Brunswick Unit 1 Cycle 23 Reactivity Margin Summary .......................................3-5 List of Figures Figure 2.1 Brunswick Unit 1 Cycle 23 Design Step-through k-eff versus Cycle Exposure .............................................................................................................2-5 Figure 2.2 Brunswick Unit 1 Cycle 23 Design Margin to Thermal Limits versus Cycle Exposure .............................................................................................................2-5 Figure 3.1 Brunswick Unit 1 Cycle 23 Reference Loading Pattern ........................................3-6 Figure 3.2 Brunswick Unit 1 Cycle 23 Upper Left Quarter Core Layout by Fuel Type ...........3-7 Figure 3.3 Brunswick Unit 1 Cycle 23 Upper Right Quarter Core Layout by Fuel Type .........3-8 Figure 3.4 Brunswick Unit 1 Cycle 23 Lower Left Quarter Core Layout by Fuel Type ...........3-9 Figure 3.5 Brunswick Unit 1 Cycle 23 Lower Right Quarter Core Layout by Fuel Type .......3-10
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page iv Nomenclature Acronym Definition
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| [] Square brackets enclose information that is proprietary to Framatome.
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| ACE Framatome critical power correlation [
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| ]
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| BOC beginning of cycle BOL beginning of life BWR boiling water reactor CSDM cold shutdown margin EOC end of cycle EOFP end of full power capability FFTR final feedwater temperature reduction GWd/MTU gigawatt days per metric ton of initial uranium HEXR hot excess reactivity LHGR linear heat generation rate MCPR minimum critical power ratio MICROBURN-B2 Framatome Inc. advanced BWR core simulator methodology with PPR capability MWd/MTU megawatt days per metric ton of initial uranium NEOC near end of cycle (MCPR limit exposure breakpoint)
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| NRC (United States) Nuclear Regulatory Commission PPR Pin Power Reconstruction. The PPR methodology accounts for variation in local rod power distributions due to neighboring assemblies and control state. The local rod power distributions are reconstructed based on the actual flux solution for each statepoint.
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| R Value the larger of zero or the shutdown margin at BOC minus the minimum calculated shutdown margin in the cycle SLC standby liquid control
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 1-1
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| ==1.0 INTRODUCTION==
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| Framatome Inc. has performed a fuel cycle design evaluation for the Brunswick Unit 1 reactor.
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| This design uses fresh ATRIUM 11 and co-resident ATRIUM 10XM fuel assemblies in the MELLLA+ operating domain. This analysis has been performed with the approved Framatome neutronic modeling methodology (Reference 1). This analysis has also used the References 2 -
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| 3 critical power methodology. The CASMO-4 lattice depletion code was used to generate nuclear data including cross section libraries and local power peaking factors. The MICROBURN-B2 three dimensional core simulator code, combined with the ACE critical power correlation, was used to model the core. The MICROBURN-B2 pin power reconstruction (PPR) model was used to determine the thermal margins presented in this report. Design results including projected control rod patterns and evaluations of thermal and reactivity margins are presented in this report. The Cycle 23 results are based on Cycle 22 core operational history as summarized in Table 2.1.
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| The following MICROBURN-B2 version 2 modeling features were also used in the analyses supporting this document:
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| * Control Blade Boron (10B) Depletion
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| * Explicit neutronic treatment of spacer grids
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| * Explicit modeling of PLFR plenums
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| * Explicit modeling of the water rod flow
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 2-1 2.0
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| ==SUMMARY==
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| The Cycle 23 fresh batch size [ ] and batch average enrichment [
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| ] were determined to meet the energy requirements provided by Duke Energy*
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| (Reference 4). For a complete description of the fresh reload assemblies, see Reference 5.
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| The loading of the Cycle 23 fuel as described in this report results in a projected Cycle 23 full power energy capability (including FFTR) of 1,964+/-30 GWd (19,344+/-300 MWd/MTU). Beyond the full power capability, the cycle has been designed to achieve 41 GWd additional energy via Constant Pressure Power Coastdown operation.
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| In order to obtain optimum operating flexibility, the projected control rod patterns for Cycle 23 were developed to be consistent with a conservative margin to thermal limits (Reference 6).
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| The cycle design calculations also demonstrate adequate hot excess reactivity and cold shutdown margin throughout the cycle. Key results from the design analysis are summarized in Table 2.1. Table 2.2 summarizes the assembly identification range by nuclear fuel type batch for the Cycle 23 design. Table 2.3, Table 2.4 and Table 2.5 contain the assumed thermal limits for this design. Figures 2.1 and 2.2 provide a summary of the cycle design step-through projection.
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| * This revised report reflects the revised design created by Duke Energy.
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 2-2 Table 2.1 Brunswick Unit 1 Cycle 23 Energy and Key Results Summary Cycle Energy, GWd (Cycle Exposure, MWd/MTU)
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| Cycle 22
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| * Core follow through January 2019 (7,774)
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| * Best estimate depletion to Nominal EOC 22 (18,800)
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| * Short window EOC 22 (18,300)
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| * Long window EOC 22 (19,000)
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| Cycle 23
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| * EOFP Energy (including FFTR) 1,964+/-30 (19,344+/-300)
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| * Constant Pressure Power Coastdown Energy 41 (403)
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| * EOC Energy (Nominal) 2,005+/-30 (19,747+/-300)
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| Key Results BOC CSDM, %k/k (based on short EOC 22) 1.07 Minimum CSDM, %k/k (based on short EOC 22) 1.07 Cycle Exposure of Minimum CSDM, MWd/MTU (short basis) 0 Moderator Temperature of Minimum CSDM, °F (short basis) 68 Cycle R Value, %k/k (short basis) 0.00 Minimum SLC SDM, %k/k (based on short EOC 22) 1.01 Cycle Exposure of Minimum SLC SDM, MWd/MTU (short basis) 0 BOC HEXR, %k/k (based on nominal EOC 22) 2.10 Maximum HEXR, %k/k (based on nominal EOC 22) 2.14 Cycle Exposure of Maximum HEXR, MWd/MTU (nominal basis) 4,000 Minimum MAPLHGR Margin, % 8.1 Exposure of Minimum MAPLHGR Margin, MWd/MTU 8,400 Minimum LHGR Margin, % 8.6 Exposure of Minimum LHGR Margin, MWd/MTU 0 Minimum CPR Margin, % 5 Exposure of Minimum CPR Margin, MWd/MTU 0
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 2-3 Table 2.2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Assembly ID Range by Nuclear Fuel Type Table 2.3 Assumed ATRIUM 11 MCPR Operating Limit
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 2-4 Table 2.4 Assumed ATRIUM 11 LHGR Limit Table 2.5 Assumed ATRIUM 11 APLHGR Limit
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 2-5 1.010 1.005 k-eff 1.000 0.995 Target
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| /ycle 23 0.990 0 2 4 6 8 10 12 14 16 18 20 22 Cycle Exposure (GWd/MTU)
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| Figure 2.1 Brunswick Unit 1 Cycle 23 Design Step-through k-eff versus Cycle Exposure 1.0 Fraction to Thermal Limits 0.9 0.8 a/tR 0.7 LHGR AtLHGR 0.6 0 2 4 6 8 10 12 14 16 18 20 22 Cycle Exposure (GWd/MTU)
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| Figure 2.2 Brunswick Unit 1 Cycle 23 Design Margin to Thermal Limits versus Cycle Exposure
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 3-1 3.0 CYCLE 23 FUEL CYCLE DESIGN 3.1 General Description The assembly design for the Cycle 23 BRK1-23 fresh reload fuel for Brunswick Unit 1 is described in detail in Reference 5. Elevation views of the fresh reload fuel design axial enrichment and gadolinia distributions are shown in Appendix B, Figures B.1 through B.3. The loading pattern generally maintains eighth core symmetry and uses a scatter load fuel management scheme. This loading in conjunction with the control rod patterns presented in Appendix A shows acceptable power peaking and associated margins to limits for projected Cycle 23 operation. The analyses supporting this fuel cycle design were based on the core parameters shown in Table 3.1. Figures 3.1 through 3.5, along with Table 3.1 define the reference loading pattern used in the fuel cycle design. The specific core location of the fresh assemblies in Cycle 23 is provided in Appendix C. Key results for the cycle are summarized in Table 2.1. Exposure limits have been checked using the long cycle N-1 and long cycle N energy window. It has been confirmed that no rod-averaged exposure exceeds 60 GWd/MTU.
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| 3.2 Control Rod Patterns and Thermal Limits Projected control rod patterns for Cycle 23 and resultant key operating parameters including thermal margins are shown in Appendix A. The thermal margins presented in this report were determined using the MICROBURN-B2 3D core simulator PPR model to provide adequate margin to thermal limits. A detailed summary of the core parameters resulting from the step-through projection analysis is provided in Tables A.1 and A.2. Limiting results from the step-through are summarized in Table 2.1 and in Figure 2.2. The thermal margins presented in this report are based on the assumed thermal limits shown in Table 2.3, Table 2.4, & Table 2.5 and are subject to revision pending the completion of the cycle thermal-mechanical and safety analyses. The hot operating target k-eff versus cycle exposure which was determined to be appropriate for Cycle 23 is shown in Table 3.2. The k-eff and margin to limits results from the design cycle depletion are presented graphically in Figure 2.1 and Figure 2.2. The k-eff values presented in Figure 2.1 and in Appendix A are not bias corrected. Selected exposure and radial power distributions from the design step-through are presented in Appendix D. The maximum core exit void fraction for the design step-through was determined to be 89.35%. The radial peaking factor does not exceed 1.60 for ATRIUM 11 fuel or 1.59 for ATRIUM 10XM fuel.
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 3-2 3.3 Hot Excess Reactivity and Cold Shutdown Margin The cycle design calculations demonstrate adequate hot excess reactivity, SLC shutdown margin, and cold shutdown margin throughout the cycle. Key shutdown margin and R-Value results are presented in Table 2.1. The shutdown margin for Cycle 23 is in conformance with the Technical Specification limit of R + 0.38 %k/k at BOC. The cold target k-eff versus exposure determined to be appropriate for calculation of cold shutdown margin in Cycle 23 is shown in Table 3.3. The core hot excess reactivity was calculated at full power with all rods out, 77.0 Mlb/hr core flow, with equilibrium xenon. Table 3.4 summarizes the Cycle 23 reactivity margins versus cycle exposure, including the SLC shutdown margin for the cycle. Cold shutdown margin calculations have also been performed at temperatures above 68 °F to determine the shutdown margin at the most reactive temperature.
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 3-3 Table 3.1 Cycle 23 Core Composition and Design Parameters Number of Fuel Assemblies in Core 560 Total Number of Fresh Assemblies [ ]
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| Total Core Mass, MTU 101.54 Rated Thermal Power Level, MW t 2,923 Rated Core Flow, Mlb/hr 77.0 Reference Pressure, psia 1,045*
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| Reference Inlet Subcooling, Btu/lbm 21.3
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| * Value is representative of MICROBURN-B2 input for dome pressure at rated conditions and varies depending on core state point.
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| Value is typically determined by MICROBURN-B2 using a heat balance method based on nominal feedwater temperature and other parameters identified in the cycle specific plant parameters document.
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 3-4 Table 3.2 Brunswick Unit 1 Cycle 23 Hot Operating Target k-eff Versus Cycle Exposure Cycle Exposure Hot Operating (MWd/MTU) k-eff*
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| 0.0 1.001 4,000.0 0.9995 9,000.0 0.9995 13,000.0 1.0005 18,000.0 1.0005 19,300.0 0.9995 EOC 0.9995 Table 3.3 Brunswick Unit 1 Cycle 23 Cold Critical Target k-eff Versus Cycle Exposure Cycle Exposure Cold Critical (MWd/MTU) k-eff 0.0 0.9925 6,000.0 0.989 EOC 0.989
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| * Values are linearly interpolated between cycle exposure points.
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 3-5 Table 3.4 Brunswick Unit 1 Cycle 23 Reactivity Margin Summary Cold Shutdown SLC Cold Shutdown Hot Excess Cycle Exposure Margin* Margin Reactivity (MWd/MTU) (% k/k) (% k/k) (% k/k) 0 1.07 1.01 2.10 250 1.39 1.31 2.00 1,250 1.83 1.62 1.92 2,100 1.89 1.63 2.00 3,000 2.03 1.61 2.08 4,000 2.16 1.62 2.14 5,250 2.25 1.61 2.12 6,700 2.43 1.70 2.10 7,400 2.44 1.70 2.11 8,400 2.40 1.74 2.11 9,350 2.29 1.81 2.11 10,200 2.19 1.86 2.09 11,200 2.14 2.01 2.06 12,600 2.04 2.31 2.01 14,000 1.78 2.70 1.94 15,600 1.72 3.31 1.66 16,000 1.56 3.46 1.55 17,000 1.29 3.88 1.07 17,800 1.23 4.28 0.56 18,150 1.26 4.48 0.30 18,950 1.39 4.99 --
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| 19,150 1.44 5.13 --
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| 19,344 1.50 5.27 --
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| 19,747 1.68 5.60 --
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| 20,200 1.95 6.01 --
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| * Based on short window EOC 22. Values for cold shutdown margin are shown in bold font if the most reactive temperature is greater than 68 °F.
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| Based on short window EOC 22, calculated at 360.8 °F ARO conditions.
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| Based on nominal EOC 22.
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 3-6 Figure 3.1 Brunswick Unit 1 Cycle 23 Reference Loading Pattern
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 3-7 Figure 3.2 Brunswick Unit 1 Cycle 23 Upper Left Quarter Core Layout by Fuel Type
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 3-8 Figure 3.3 Brunswick Unit 1 Cycle 23 Upper Right Quarter Core Layout by Fuel Type
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 3-9 Figure 3.4 Brunswick Unit 1 Cycle 23 Lower Left Quarter Core Layout by Fuel Type
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 3-10 Figure 3.5 Brunswick Unit 1 Cycle 23 Lower Right Quarter Core Layout by Fuel Type
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page 4-1
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| ==4.0 REFERENCES==
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| : 1. 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.
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| : 2. ANP-10298(P) Revision 1, ACE/ATRIUM 10XM Critical Power Correlation, AREVA, March 2014.
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| : 3. ANP-10335P-A, Revision 0, ACE/ATRIUM 11 Critical Power Correlation, Framatome Inc., May 2018
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| : 4. FS1-0040620 Revision 1.0, BRK1-23 RSD Transmittal Revision 1 NF18-73, October 2018.
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| : 5. ANP-3758P, Revision 1, Nuclear Fuel Design Report Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel, September 2019.
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| : 6. FS1-0040610, Revision 1.0, Brunswick Unit 1 Cycle 23 Target K-Effective and Thermal Limit Selection, October 2018.
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-1 Appendix A Brunswick Unit 1 Cycle 23 Step-through Depletion Summary, Control Rod Patterns and Core Average Axial Power and Exposure Distributions
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-2 Table A.1 Brunswick Unit 1 Cycle 23 Design Depletion Summary Total Total Inlet Core Core Cycle Control Core Core Ref. Sub- Core Maximum Maximum Exposure Calculated Rod Power Flow Pressure Cooling Void Minimum LHGR APLHGR (GWd/MT) K-eff Density MWt (Mlb/hr) (psia) (Btu/lb) Fraction CPR (kW/ft) (kW/ft) 0.000 1.00125 6.20 2923.0 68.92 1044.70 24.16 0.532 1.446 12.43 10.24 0.250 1.00083 6.20 2923.0 70.84 1044.71 23.43 0.523 1.493 12.17 10.07 0.750 1.00055 6.20 2923.0 74.31 1044.75 22.21 0.513 1.527 12.19 10.08 1.250 1.00041 6.20 2923.0 73.15 1044.74 22.60 0.517 1.515 12.25 10.11 1.750 1.00010 6.20 2923.0 71.03 1044.72 23.36 0.523 1.500 12.24 10.12 2.100 0.99993 6.20 2923.0 69.68 1044.70 23.87 0.528 1.491 12.24 10.20 2.101 1.00019 6.57 2923.0 71.61 1044.72 23.15 0.511 1.449 12.30 9.89 2.500 1.00009 6.57 2923.0 70.46 1044.71 23.57 0.515 1.451 12.16 9.86 3.000 0.99991 6.57 2923.0 69.30 1044.70 24.02 0.519 1.457 12.03 9.82 3.500 0.99967 6.57 2923.0 68.14 1044.69 24.47 0.523 1.456 11.87 9.74 4.000 0.99949 6.57 2923.0 67.38 1044.68 24.78 0.526 1.456 11.86 9.64 4.400 0.99949 6.57 2923.0 67.38 1044.68 24.79 0.525 1.462 11.83 9.55 4.800 0.99946 6.57 2923.0 67.38 1044.68 24.79 0.524 1.468 11.77 9.48 4.801 0.99967 6.66 2923.0 69.68 1044.70 23.87 0.526 1.483 11.98 9.67 5.250 0.99957 6.66 2923.0 69.68 1044.70 23.87 0.525 1.485 11.85 9.61 5.700 0.99957 6.66 2923.0 69.88 1044.71 23.79 0.523 1.490 11.78 9.55 6.200 0.99957 6.66 2923.0 70.07 1044.71 23.72 0.521 1.493 11.70 9.57 6.700 0.99959 6.66 2923.0 70.26 1044.71 23.65 0.519 1.495 11.62 9.62 7.100 0.99953 6.66 2923.0 70.07 1044.71 23.72 0.519 1.492 11.57 9.65 7.400 0.99950 6.66 2923.0 69.88 1044.71 23.79 0.519 1.489 11.52 9.67 7.401 0.99966 6.39 2923.0 67.18 1044.68 24.86 0.532 1.448 11.89 9.65 7.900 0.99963 6.39 2923.0 67.38 1044.68 24.79 0.530 1.457 11.78 9.61 8.400 0.99965 6.39 2923.0 67.38 1044.68 24.79 0.529 1.463 11.69 9.65 8.850 0.99967 6.39 2923.0 67.38 1044.68 24.79 0.527 1.467 11.60 9.65 9.350 0.99971 6.39 2923.0 67.38 1044.68 24.79 0.525 1.471 11.41 9.57 9.351 0.99985 6.11 2923.0 66.61 1044.68 25.10 0.522 1.492 11.59 9.75 9.700 0.99986 6.11 2923.0 66.61 1044.68 25.11 0.519 1.491 11.35 9.61 10.200 1.00000 6.11 2923.0 66.99 1044.68 24.94 0.514 1.492 10.90 9.31 10.700 1.00015 6.11 2923.0 67.38 1044.68 24.79 0.507 1.490 10.37 8.89 11.200 1.00025 6.11 2923.0 67.57 1044.68 24.71 0.499 1.486 9.81 8.42 11.700 1.00037 6.11 2923.0 67.76 1044.69 24.63 0.491 1.481 9.20 7.96 12.100 1.00048 6.11 2923.0 68.14 1044.69 24.47 0.483 1.482 8.84 7.75 12.101 1.00036 5.44 2923.0 68.14 1044.69 24.47 0.501 1.463 10.54 9.04 12.600 1.00048 5.44 2923.0 68.92 1044.70 24.17 0.489 1.469 9.71 8.31 13.100 1.00059 5.44 2923.0 69.45 1044.70 23.96 0.478 1.465 9.05 7.78 13.600 1.00069 5.44 2923.0 70.07 1044.71 23.72 0.467 1.463 9.16 7.60 14.000 1.00080 5.44 2923.0 70.84 1044.71 23.43 0.458 1.463 9.21 7.66 14.400 1.00077 5.44 2923.0 71.61 1044.72 23.15 0.449 1.464 9.30 7.77 14.850 1.00074 5.44 2923.0 72.76 1044.73 22.74 0.438 1.468 9.37 7.91 14.851 1.00043 5.38 2923.0 72.38 1044.73 22.87 0.437 1.454 9.69 8.53 15.200 1.00037 5.38 2923.0 74.31 1044.75 22.21 0.427 1.504 9.60 8.55 15.600 1.00048 5.38 2923.0 77.00 1044.77 21.33 0.415 1.560 9.54 8.58 16.000 1.00060 5.38 2923.0 80.46 1044.80 20.29 0.401 1.609 9.52 8.59 16.001 1.00024 4.81 2923.0 68.92 1044.70 24.15 0.415 1.477 9.85 8.81 16.500 1.00035 4.81 2923.0 73.92 1044.74 22.34 0.397 1.533 10.03 8.98 17.000 1.00059 4.81 2923.0 80.46 1044.80 20.29 0.377 1.574 10.21 9.15 17.001 1.00030 3.65 2923.0 72.76 1044.73 22.73 0.400 1.494 9.78 8.82 17.500 1.00034 3.65 2923.0 80.46 1044.80 20.29 0.377 1.539 10.08 9.02 17.501 1.00017 2.55 2923.0 74.31 1044.75 22.20 0.397 1.473 10.41 8.81 17.800 1.00038 2.55 2923.0 80.46 1044.80 20.29 0.381 1.513 10.45 8.91 17.801 1.00038 1.46 2923.0 73.15 1044.74 22.59 0.400 1.495 10.38 8.79 18.150 1.00036 1.46 2923.0 80.46 1044.80 20.29 0.381 1.548 10.41 8.93 18.151 1.00057 0.64 2923.0 73.92 1044.74 22.33 0.393 1.502 10.29 8.81 18.500 1.00012 0.64 2923.0 80.46 1044.80 20.29 0.376 1.564 10.24 8.87 18.501 1.00029 0.00 2923.0 76.23 1044.76 21.56 0.386 1.516 10.35 8.87 18.739 0.99974 0.00 2923.0 80.46 1044.80 20.29 0.375 1.550 10.34 8.94 18.740 0.99995 0.00 2923.0 76.23 1044.70 25.15 0.372 1.538 10.11 8.73 18.950 0.99973 0.00 2923.0 80.46 1044.70 23.68 0.361 1.570 10.13 8.81 18.951 0.99970 0.00 2923.0 76.23 1044.70 28.45 0.359 1.560 9.93 8.61 19.150 0.99958 0.00 2923.0 80.46 1044.70 26.80 0.348 1.590 9.98 8.71 19.151 0.99942 0.00 2923.0 76.23 1044.70 31.50 0.347 1.579 9.78 8.51 19.344 0.99926 0.00 2923.0 80.46 1044.70 29.69 0.337 1.608 9.84 8.61 19.747 0.99964 0.00 2649.7 80.46 1044.70 26.71 0.315 1.751 9.00 7.99 20.200 0.99955 0.00 2389.7 80.46 1044.70 23.87 0.293 1.916 8.20 7.40 20.697 0.99931 0.00 2111.8 80.46 1044.70 20.83 0.269 2.138 7.52 6.72
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-3 Table A.2 Brunswick Unit 1 Cycle 23 Design Depletion Thermal Margin Summary Fraction Core Fraction Core Fraction Cycle Control Core of Limiting of Limiting of Exposure Calculated Rod Limiting Limiting LHGR Limiting APLHGR Limiting (GWd/MT) K-eff Density CPR CPR (kW/ft) LHGR (kW/ft) APLHGR 0.000 1.00125 6.204 1.446 0.954 12.43 0.914 10.24 0.867 0.250 1.00083 6.204 1.493 0.925 12.17 0.895 10.06 0.856 0.750 1.00055 6.204 1.527 0.903 12.19 0.896 10.08 0.865 1.250 1.00041 6.204 1.515 0.911 12.25 0.900 10.11 0.877 1.750 1.00010 6.204 1.500 0.920 12.24 0.900 10.12 0.886 2.100 0.99993 6.204 1.491 0.925 12.24 0.900 10.20 0.899 2.101 1.00019 6.569 1.449 0.952 12.30 0.905 9.89 0.882 2.500 1.00009 6.569 1.451 0.951 12.16 0.894 9.86 0.886 3.000 0.99991 6.569 1.457 0.947 12.03 0.884 9.82 0.890 3.500 0.99967 6.569 1.456 0.948 10.52 0.881 9.74 0.892 4.000 0.99949 6.569 1.456 0.948 10.38 0.877 9.64 0.891 4.400 0.99949 6.569 1.462 0.944 10.26 0.873 9.55 0.890 4.800 0.99946 6.569 1.468 0.940 10.13 0.869 9.46 0.888 4.801 0.99967 6.661 1.483 0.931 11.98 0.881 9.50 0.896 5.250 0.99957 6.661 1.485 0.929 10.56 0.880 9.44 0.897 5.700 0.99957 6.661 1.490 0.926 10.49 0.882 9.39 0.901 6.200 0.99957 6.661 1.493 0.924 10.41 0.883 9.33 0.903 6.700 0.99959 6.661 1.495 0.923 10.33 0.884 9.27 0.906 7.100 0.99953 6.661 1.492 0.925 10.24 0.883 9.22 0.909 7.400 0.99950 6.661 1.489 0.927 10.16 0.882 9.18 0.910 7.401 0.99966 6.387 1.448 0.953 10.38 0.901 9.45 0.916 7.900 0.99963 6.387 1.457 0.947 10.29 0.902 9.37 0.917 8.400 0.99965 6.387 1.463 0.943 10.20 0.902 9.29 0.919 8.850 0.99967 6.387 1.467 0.940 10.10 0.900 9.20 0.918 9.350 0.99971 6.387 1.471 0.938 9.93 0.894 9.05 0.912 9.351 0.99985 6.113 1.492 0.925 10.00 0.888 9.14 0.909 9.700 0.99986 6.113 1.491 0.926 9.74 0.871 8.90 0.892 10.200 1.00000 6.113 1.492 0.925 9.38 0.846 8.58 0.868 10.700 1.00015 6.113 1.490 0.926 8.98 0.818 8.23 0.840 11.200 1.00025 6.113 1.486 0.929 8.02 0.794 7.86 0.810 11.700 1.00037 6.113 1.481 0.932 7.68 0.776 7.48 0.776 12.100 1.00048 6.113 1.482 0.931 7.40 0.761 7.48 0.764 12.101 1.00036 5.444 1.463 0.943 7.76 0.809 7.85 0.820 12.600 1.00048 5.444 1.469 0.940 7.45 0.783 7.30 0.778 13.100 1.00059 5.444 1.465 0.942 7.19 0.764 6.98 0.745 13.600 1.00069 5.444 1.463 0.943 6.90 0.748 7.45 0.733 14.000 1.00080 5.444 1.463 0.943 7.54 0.748 7.58 0.750 14.400 1.00077 5.444 1.464 0.943 8.54 0.763 7.70 0.767 14.850 1.00074 5.444 1.468 0.940 8.70 0.784 7.87 0.786 14.851 1.00043 5.383 1.454 0.949 9.19 0.838 8.44 0.849 15.200 1.00037 5.383 1.504 0.918 9.10 0.836 8.31 0.846 15.600 1.00048 5.383 1.560 0.885 9.03 0.835 8.25 0.845 16.000 1.00060 5.383 1.609 0.858 9.15 0.834 8.38 0.844 16.001 1.00024 4.805 1.477 0.935 9.28 0.840 8.48 0.851 16.500 1.00035 4.805 1.533 0.900 10.03 0.856 8.42 0.852 17.000 1.00059 4.805 1.574 0.889 10.21 0.879 9.00 0.872 17.001 1.00030 3.650 1.494 0.937 9.78 0.843 8.82 0.841 17.500 1.00034 3.650 1.539 0.910 10.00 0.871 9.02 0.868 17.501 1.00017 2.555 1.473 0.950 9.59 0.875 8.69 0.874 17.800 1.00038 2.555 1.513 0.925 9.66 0.886 8.76 0.887 17.801 1.00038 1.460 1.495 0.936 8.84 0.868 8.63 0.873 18.150 1.00036 1.460 1.548 0.904 8.97 0.896 8.69 0.885 18.151 1.00057 0.639 1.502 0.932 9.44 0.871 8.55 0.871 18.500 1.00012 0.639 1.564 0.895 8.78 0.891 8.60 0.882 18.501 1.00029 0.000 1.516 0.924 8.62 0.884 8.64 0.881 18.739 0.99974 0.000 1.550 0.910 8.63 0.896 8.64 0.888 18.740 0.99995 0.000 1.538 0.917 8.49 0.881 8.44 0.868 18.950 0.99973 0.000 1.570 0.898 8.63 0.895 8.51 0.879 18.951 0.99970 0.000 1.560 0.904 8.51 0.883 8.33 0.860 19.150 0.99958 0.000 1.590 0.887 8.60 0.900 8.42 0.872 19.151 0.99942 0.000 1.579 0.893 8.47 0.887 8.24 0.853 19.344 0.99926 0.000 1.608 0.877 8.57 0.905 8.33 0.866 19.747 0.99964 0.000 1.751 0.805 7.90 0.851 7.74 0.807 20.200 0.99955 0.000 1.916 0.736 7.22 0.796 7.25 0.753 20.697 0.99931 0.000 2.138 0.660 6.46 0.731 6.59 0.692
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-4 Cycle: 23 Core Average Exposure: MWd/MTU 16658.3 Exposure: MWd/MTU (GWd) 0.0 ( 0.00 )
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| Delta E: MWd/MTU, (GWd) 0.0 ( 0.00 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.128 3.306 37 0.758 0.791 3 24 Inlet Subcooling: Btu/lbm -24.16 24 0.298 9.241 38 0.462 0.690 47 16 Flow: Mlb/hr 68.92 ( 89.50 %) 23 0.476 11.702 39 0.486 0.848 17 48 22 0.569 13.900 40 0.558 1.008 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.628 15.411 41 0.907 1.250 39 38 51 -- -- -- -- -- 51 20 0.677 16.527 42 1.174 1.358 31 24 47 -- -- -- -- -- -- -- -- -- 47 19 0.719 17.124 43 1.278 1.398 27 22 43 -- -- -- -- -- 8 -- -- -- -- -- 43 18 0.771 17.814 44 1.091 1.293 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.824 18.294 45 1.136 1.329 39 22 35 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 35 16 0.890 18.544 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.975 18.678 27 -- -- 8 -- 40 -- 0 -- 40 -- 8 -- -- 27 14 1.034 18.678 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.147 18.774 19 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 19 12 1.219 19.393 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.275 19.788 11 -- -- -- -- -- 8 -- -- -- -- -- 11 10 1.353 19.488 7 -- -- -- -- -- -- -- -- -- 7 9 1.376 19.810 3 -- -- -- -- -- 3 8 1.403 19.962 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.437 20.038 6 1.473 20.357*
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| 5 1.515 20.283 4 1.550 19.602 Control Rod Density: % 6.20 3 1.591* 18.162 2 1.326 14.002 k-effective: 1.00125 Bottom 1 0.346 4.024 Void Fraction: 0.532 Core Delta-P: psia 20.394 % AXIAL TILT -33.013 -9.236 Core Plate Delta-P: psia 15.840 AVG BOT 8ft/12ft 1.2007 1.0560 Coolant Temp: Deg-F 548.6 In Channel Flow: Mlb/hr 59.90 Active Channel Flow: Mlb/hr 57.64 Total Bypass Flow (%): 13.1 (of total core flow)
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| Total Water Rod Flow (%): 3.3 (of total core flow)
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| Source Convergence 0.00040 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.398 43 27 22 1.446 0.954 43 21 28 10.24 0.867 27.4 42 19 26 6 12.43 0.914 0.0 43 17 28 6 1.395 43 31 26 1.455 0.948 43 19 30 10.15 0.863 27.9 42 27 20 6 12.36 0.909 0.0 43 27 18 6 1.391 43 33 24 1.456 0.948 43 27 22 9.56 0.799 25.9 41 13 38 3 12.14 0.893 0.0 43 21 28 6 1.391 43 29 20 1.468 0.940 43 29 20 9.43 0.797 27.2 41 37 14 3 12.08 0.888 0.0 43 19 30 6 1.384 43 29 24 1.472 0.938 45 39 22 9.41 0.796 27.3 42 21 24 6 12.08 0.888 0.0 44 13 36 3 1.374 43 31 22 1.478 0.934 43 23 24 9.37 0.794 27.5 42 23 22 6 12.07 0.888 0.0 43 27 22 6 1.358 42 31 24 1.482 0.931 45 31 14 9.42 0.786 25.7 42 13 34 3 12.07 0.888 0.0 44 39 14 3 1.356 42 29 22 1.486 0.929 43 21 22 9.25 0.781 27.2 42 17 30 6 12.02 0.884 0.0 44 35 40 3 1.354 43 37 24 1.503 0.918 45 39 26 9.11 0.779 28.6 42 29 18 6 12.01 0.883 0.0 43 29 20 6 1.353 42 35 24 1.507 0.916 44 35 14 9.28 0.778 26.3 42 33 14 3 11.96 0.879 0.0 45 13 32 3
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| * LHGR calculated with pin-power reconstruction
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| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.1 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 0.0 MWd/MTU
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-5 Cycle: 23 Core Average Exposure: MWd/MTU 16908.2 Exposure: MWd/MTU (GWd) 250.0 ( 25.39 )
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| Delta E: MWd/MTU, (GWd) 250.0 ( 25.39 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.134 3.341 37 0.764 0.798 3 24 Inlet Subcooling: Btu/lbm -23.43 24 0.312 9.324 38 0.465 0.693 47 16 Flow: Mlb/hr 70.84 ( 92.00 %) 23 0.498 11.834 39 0.489 0.852 17 48 22 0.594 14.058 40 0.561 1.013 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.654 15.586 41 0.911 1.250 39 38 51 -- -- -- -- -- 51 20 0.702 16.715 42 1.175 1.357 31 24 47 -- -- -- -- -- -- -- -- -- 47 19 0.743 17.323 43 1.272 1.391 27 22 43 -- -- -- -- -- 8 -- -- -- -- -- 43 18 0.792 18.027 44 1.089 1.287 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.844 18.521 45 1.133 1.323 39 22 35 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 35 16 0.906 18.786 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.988 18.936 27 -- -- 8 -- 40 -- 0 -- 40 -- 8 -- -- 27 14 1.044 18.951 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.154 19.052 19 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 19 12 1.223 19.687 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.276 20.096 11 -- -- -- -- -- 8 -- -- -- -- -- 11 10 1.351 19.800 7 -- -- -- -- -- -- -- -- -- 7 9 1.373 20.127 3 -- -- -- -- -- 3 8 1.396 20.285 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.427 20.368 6 1.457 20.695*
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| 5 1.491 20.630 4 1.511 19.955 Control Rod Density: % 6.20 3 1.532* 18.522 2 1.267 14.301 k-effective: 1.00083 Bottom 1 0.330 4.108 Void Fraction: 0.523 Core Delta-P: psia 21.119 % AXIAL TILT -31.124 -9.474 Core Plate Delta-P: psia 16.563 AVG BOT 8ft/12ft 1.1900 1.0574 Coolant Temp: Deg-F 548.6 In Channel Flow: Mlb/hr 61.65 Active Channel Flow: Mlb/hr 59.34 Total Bypass Flow (%): 13.0 (of total core flow)
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| Total Water Rod Flow (%): 3.2 (of total core flow)
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| Source Convergence 0.00047 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.391 43 27 22 1.493 0.925 43 21 28 10.06 0.856 28.0 42 19 28 6 12.17 0.895 0.8 43 17 28 6 1.388 43 21 28 1.497 0.922 43 27 22 9.97 0.852 28.4 42 27 20 6 12.08 0.889 0.8 43 27 18 6 1.384 43 33 24 1.501 0.919 45 39 22 9.30 0.790 27.8 42 21 24 6 11.91 0.876 0.8 43 21 28 6 1.384 43 29 20 1.502 0.919 43 19 30 9.26 0.788 28.0 42 23 22 6 11.86 0.872 0.8 43 19 30 6 1.377 43 29 24 1.507 0.916 43 29 20 9.15 0.776 27.6 42 17 30 6 11.83 0.870 0.8 43 27 22 6 1.366 43 31 22 1.510 0.914 45 31 14 9.23 0.774 26.4 41 13 38 3 11.78 0.866 0.8 43 29 20 6 1.357 42 31 24 1.524 0.905 43 23 24 9.00 0.773 29.0 42 29 18 6 11.00 0.862 32.4 42 19 28 6 1.355 42 29 22 1.529 0.903 45 39 26 9.09 0.771 27.7 41 37 14 3 10.91 0.858 32.7 42 27 20 6 1.351 42 35 24 1.533 0.900 43 21 22 9.10 0.763 26.2 42 13 34 3 11.53 0.848 0.8 44 13 36 3 1.347 43 37 24 1.535 0.899 44 35 14 8.82 0.762 29.7 42 23 28 6 11.51 0.846 0.8 44 39 40 3
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| * LHGR calculated with pin-power reconstruction
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| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.2 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 250.0 MWd/MTU
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-6 Cycle: 23 Core Average Exposure: MWd/MTU 17408.2 Exposure: MWd/MTU (GWd) 750.0 ( 76.16 )
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| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.140 3.415 37 0.761 0.795 3 24 Inlet Subcooling: Btu/lbm -22.21 24 0.326 9.495 38 0.460 0.688 47 16 Flow: Mlb/hr 74.31 ( 96.50 %) 23 0.518 12.110 39 0.484 0.849 17 48 22 0.614 14.386 40 0.557 1.010 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.672 15.947 41 0.908 1.253 37 14 51 -- -- -- -- -- 51 20 0.717 17.101 42 1.176 1.357 31 24 47 -- -- -- -- -- -- -- -- -- 47 19 0.754 17.731 43 1.277 1.396 27 22 43 -- -- -- -- -- 8 -- -- -- -- -- 43 18 0.799 18.460 44 1.090 1.292 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.847 18.982 45 1.135 1.328 39 22 35 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 35 16 0.906 19.275 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.984 19.455 27 -- -- 8 -- 40 -- 0 -- 40 -- 8 -- -- 27 14 1.037 19.499 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.146 19.607 19 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 19 12 1.214 20.275 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.267 20.709 11 -- -- -- -- -- 8 -- -- -- -- -- 11 10 1.343 20.424 7 -- -- -- -- -- -- -- -- -- 7 9 1.370 20.759 3 -- -- -- -- -- 3 8 1.397 20.928 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.430 21.027 6 1.464 21.368*
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| 5 1.494 21.318 4 1.502 20.650 Control Rod Density: % 6.20 3 1.502* 19.221 2 1.232 14.876 k-effective: 1.00055 Bottom 1 0.326 4.271 Void Fraction: 0.513 Core Delta-P: psia 22.554 % AXIAL TILT -30.296 -9.889 Core Plate Delta-P: psia 17.996 AVG BOT 8ft/12ft 1.1834 1.0598 Coolant Temp: Deg-F 548.6 In Channel Flow: Mlb/hr 64.76 Active Channel Flow: Mlb/hr 62.38 Total Bypass Flow (%): 12.8 (of total core flow)
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| Total Water Rod Flow (%): 3.2 (of total core flow)
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| Source Convergence 0.00045 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.396 43 27 22 1.527 0.903 43 21 28 10.08 0.865 29.0 42 19 26 6 12.19 0.896 2.3 43 17 28 6 1.392 43 21 28 1.534 0.899 43 19 30 9.98 0.861 29.5 42 27 20 6 12.10 0.890 2.3 43 27 36 6 1.390 43 33 24 1.535 0.899 43 27 22 9.33 0.800 28.8 42 21 24 6 11.94 0.878 2.3 43 21 28 6 1.390 43 29 20 1.536 0.898 45 39 22 9.29 0.798 29.0 42 23 22 6 11.90 0.875 2.3 43 19 30 6 1.380 43 29 24 1.544 0.894 43 29 20 9.19 0.786 28.6 42 17 30 6 11.87 0.873 2.3 43 27 22 6 1.372 43 31 22 1.545 0.893 45 31 14 9.05 0.784 30.0 42 29 18 6 11.83 0.870 2.3 43 29 20 6 1.357 42 31 24 1.558 0.886 43 23 24 8.83 0.769 30.6 42 23 28 6 10.98 0.868 33.5 42 19 28 6 1.356 42 29 22 1.563 0.883 45 39 26 8.89 0.768 29.7 42 15 28 6 10.88 0.863 33.9 42 27 20 6 1.353 42 35 24 1.566 0.881 43 21 22 9.08 0.768 27.3 41 13 38 3 11.34 0.834 2.2 43 23 30 5 1.353 43 37 24 1.570 0.879 44 35 14 8.92 0.766 29.0 42 27 16 6 11.32 0.832 2.2 43 21 22 5
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| * LHGR calculated with pin-power reconstruction
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| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.3 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 750.0 MWd/MTU
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-7 Cycle: 23 Core Average Exposure: MWd/MTU 17908.3 Exposure: MWd/MTU (GWd) 1250.0 ( 126.93 )
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| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.142 3.490 37 0.756 0.787 3 24 Inlet Subcooling: Btu/lbm -22.60 24 0.331 9.672 38 0.455 0.684 47 16 Flow: Mlb/hr 73.15 ( 95.00 %) 23 0.521 12.392 39 0.479 0.842 17 48 22 0.616 14.720 40 0.551 1.003 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.671 16.312 41 0.903 1.252 37 14 51 -- -- -- -- -- 51 20 0.712 17.490 42 1.174 1.353 31 24 47 -- -- -- -- -- -- -- -- -- 47 19 0.747 18.139 43 1.284 1.402 27 22 43 -- -- -- -- -- 8 -- -- -- -- -- 43 18 0.790 18.893 44 1.094 1.302 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.835 19.439 45 1.142 1.336 39 22 35 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 35 16 0.890 19.759 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.966 19.968 27 -- -- 8 -- 40 -- 0 -- 40 -- 8 -- -- 27 14 1.018 20.039 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.125 20.155 19 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 19 12 1.193 20.856 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.248 21.316 11 -- -- -- -- -- 8 -- -- -- -- -- 11 10 1.327 21.042 7 -- -- -- -- -- -- -- -- -- 7 9 1.363 21.389 3 -- -- -- -- -- 3 8 1.399 21.573 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.442 21.689 6 1.487 22.049*
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| 5 1.525 22.014 4 1.535* 21.350 Control Rod Density: % 6.20 3 1.528 19.919 2 1.253 15.448 k-effective: 1.00041 Bottom 1 0.336 4.435 Void Fraction: 0.517 Core Delta-P: psia 22.092 % AXIAL TILT -30.988 -10.280 Core Plate Delta-P: psia 17.535 AVG BOT 8ft/12ft 1.1849 1.0620 Coolant Temp: Deg-F 548.6 In Channel Flow: Mlb/hr 63.71 Active Channel Flow: Mlb/hr 61.36 Total Bypass Flow (%): 12.9 (of total core flow)
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| Total Water Rod Flow (%): 3.2 (of total core flow)
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| Source Convergence 0.00046 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.402 43 27 22 1.515 0.911 43 21 28 10.11 0.877 30.1 42 19 26 6 12.25 0.900 3.9 43 17 28 6 1.399 43 31 26 1.519 0.908 43 19 30 10.02 0.872 30.5 42 27 20 6 12.17 0.895 3.9 43 27 36 6 1.397 43 33 24 1.526 0.904 43 27 22 9.37 0.810 29.8 42 21 24 6 12.00 0.882 3.8 43 21 28 6 1.397 43 29 20 1.533 0.900 45 39 22 9.33 0.808 29.9 42 23 22 6 11.97 0.880 3.8 43 19 30 6 1.386 43 29 24 1.534 0.900 43 29 20 9.25 0.799 29.6 42 17 30 6 11.92 0.877 3.8 43 27 22 6 1.379 43 31 22 1.542 0.895 45 31 14 9.11 0.796 30.9 42 29 18 6 10.97 0.876 34.7 42 19 28 6 1.361 43 37 24 1.544 0.894 43 23 24 9.20 0.785 28.3 41 13 38 3 11.90 0.875 3.8 43 29 20 6 1.357 43 29 16 1.551 0.890 43 21 22 9.06 0.782 29.6 41 37 14 3 10.88 0.871 35.0 42 27 20 6 1.356 43 35 26 1.563 0.883 45 39 26 8.96 0.781 30.7 42 15 28 6 11.45 0.842 3.6 43 29 30 5 1.354 43 27 18 1.566 0.881 44 35 14 8.99 0.779 29.9 42 27 16 6 11.44 0.841 3.6 43 21 22 5
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| * LHGR calculated with pin-power reconstruction
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| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.4 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 1,250.0 MWd/MTU
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-8 Cycle: 23 Core Average Exposure: MWd/MTU 18408.2 Exposure: MWd/MTU (GWd) 1750.0 ( 177.70 )
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| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.144 3.567 37 0.751 0.780 3 24 Inlet Subcooling: Btu/lbm -23.36 24 0.334 9.851 38 0.451 0.680 47 16 Flow: Mlb/hr 71.03 ( 92.25 %) 23 0.523 12.676 39 0.475 0.836 17 48 22 0.617 15.054 40 0.546 0.996 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.668 16.677 41 0.897 1.250 37 14 51 -- -- -- -- -- 51 20 0.707 17.876 42 1.170 1.347 31 24 47 -- -- -- -- -- -- -- -- -- 47 19 0.739 18.543 43 1.290 1.406 27 22 43 -- -- -- -- -- 8 -- -- -- -- -- 43 18 0.779 19.320 44 1.099 1.311 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.821 19.890 45 1.149 1.344 39 22 35 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 35 16 0.874 20.235 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.947 20.471 27 -- -- 8 -- 40 -- 0 -- 40 -- 8 -- -- 27 14 0.997 20.569 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.103 20.692 19 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 19 12 1.171 21.426 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.228 21.913 11 -- -- -- -- -- 8 -- -- -- -- -- 11 10 1.310 21.652 7 -- -- -- -- -- -- -- -- -- 7 9 1.355 22.015 3 -- -- -- -- -- 3 8 1.400 22.218 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.454 22.356 6 1.512 22.740*
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| 5 1.559 22.725 4 1.574* 22.067 Control Rod Density: % 6.20 3 1.560 20.631 2 1.279 16.032 k-effective: 1.00010 Bottom 1 0.346 4.604 Void Fraction: 0.523 Core Delta-P: psia 21.234 % AXIAL TILT -31.781 -10.671 Core Plate Delta-P: psia 16.679 AVG BOT 8ft/12ft 1.1869 1.0641 Coolant Temp: Deg-F 548.6 In Channel Flow: Mlb/hr 61.81 Active Channel Flow: Mlb/hr 59.50 Total Bypass Flow (%): 13.0 (of total core flow)
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| Total Water Rod Flow (%): 3.2 (of total core flow)
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| Source Convergence 0.00049 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.406 43 27 22 1.500 0.920 43 21 28 10.12 0.886 31.1 42 19 26 6 12.24 0.900 5.4 43 17 28 6 1.403 43 31 26 1.503 0.918 43 19 30 10.03 0.881 31.6 42 27 20 6 12.18 0.896 5.4 43 27 36 6 1.403 43 33 24 1.511 0.913 43 27 22 9.42 0.821 30.6 42 21 24 5 10.94 0.882 35.8 42 19 28 6 1.403 43 29 20 1.516 0.910 43 29 20 9.40 0.819 30.7 42 23 22 5 11.99 0.881 5.4 43 21 28 6 1.390 43 29 24 1.524 0.905 45 39 22 9.29 0.809 30.5 42 17 30 6 11.99 0.881 5.4 43 19 30 6 1.385 43 31 22 1.529 0.903 43 23 24 9.16 0.807 31.9 42 29 18 6 10.86 0.877 36.1 42 27 20 6 1.368 43 37 24 1.533 0.900 45 31 14 9.35 0.805 29.3 41 13 38 3 11.92 0.876 5.3 43 27 22 6 1.364 43 29 16 1.535 0.899 43 21 22 9.21 0.802 30.6 41 37 14 3 11.91 0.876 5.3 43 29 20 6 1.361 43 35 26 1.557 0.886 44 35 14 9.26 0.795 29.1 42 13 34 3 11.62 0.854 5.1 44 13 36 3 1.359 43 27 18 1.558 0.886 45 39 26 9.02 0.793 31.6 42 15 28 6 11.55 0.849 5.1 43 21 22 4
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.5 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 1,750.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-9 Cycle: 23 Core Average Exposure: MWd/MTU 18758.3 Exposure: MWd/MTU (GWd) 2100.0 ( 213.24 )
| |
| Delta E: MWd/MTU, (GWd) 350.0 ( 35.54 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.145 3.621 37 0.748 0.776 3 24 Inlet Subcooling: Btu/lbm -23.87 24 0.335 9.977 38 0.448 0.677 47 16 Flow: Mlb/hr 69.68 ( 90.50 %) 23 0.524 12.875 39 0.472 0.833 17 48 22 0.616 15.288 40 0.543 0.991 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.666 16.931 41 0.894 1.249 37 14 51 -- -- -- -- -- 51 20 0.703 18.145 42 1.168 1.342 31 24 47 -- -- -- -- -- -- -- -- -- 47 19 0.733 18.824 43 1.294 1.409 27 22 43 -- -- -- -- -- 8 -- -- -- -- -- 43 18 0.771 19.615 44 1.103 1.317 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.812 20.201 45 1.153 1.349 39 22 35 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 35 16 0.863 20.563 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.934 20.817 27 -- -- 8 -- 40 -- 0 -- 40 -- 8 -- -- 27 14 0.983 20.934 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.087 21.062 19 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 19 12 1.155 21.819 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.213 22.325 11 -- -- -- -- -- 8 -- -- -- -- -- 11 10 1.299 22.075 7 -- -- -- -- -- -- -- -- -- 7 9 1.349 22.451 3 -- -- -- -- -- 3 8 1.401 22.669 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.463 22.827 6 1.530 23.231 5 1.584 23.232*
| |
| 4 1.602* 22.579 Control Rod Density: % 6.20 3 1.583 21.138 2 1.297 16.447 k-effective: 0.99993 Bottom 1 0.353 4.725 Void Fraction: 0.528 Core Delta-P: psia 20.699 % AXIAL TILT -32.383 -10.946 Core Plate Delta-P: psia 16.145 AVG BOT 8ft/12ft 1.1886 1.0655 Coolant Temp: Deg-F 548.6 In Channel Flow: Mlb/hr 60.60 Active Channel Flow: Mlb/hr 58.32 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00047 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.409 43 27 22 1.491 0.925 43 21 28 10.20 0.899 31.9 42 19 26 6 12.24 0.900 6.5 43 17 28 6 1.407 43 29 20 1.492 0.925 43 19 30 10.12 0.894 32.2 42 25 20 6 12.16 0.894 6.5 43 27 36 6 1.406 43 33 24 1.502 0.919 43 27 22 9.54 0.836 31.3 42 21 24 5 11.00 0.892 36.6 42 19 28 6 1.406 43 31 26 1.506 0.916 43 29 20 9.52 0.835 31.4 42 23 22 5 10.91 0.887 36.9 42 27 20 6 1.392 43 29 24 1.519 0.908 45 39 22 9.45 0.819 30.0 41 13 38 3 12.01 0.883 6.4 43 19 30 6 1.389 43 31 22 1.522 0.907 43 23 24 9.34 0.818 31.2 42 17 24 6 12.01 0.883 6.4 43 21 28 6 1.373 43 37 24 1.528 0.903 43 21 22 9.31 0.816 31.2 41 37 14 3 11.94 0.878 6.4 43 27 22 6 1.369 43 29 16 1.529 0.903 45 31 14 9.20 0.816 32.6 42 29 18 6 11.94 0.878 6.4 43 29 20 6 1.364 43 35 26 1.552 0.889 44 35 14 9.19 0.810 31.9 42 13 34 4 11.75 0.864 6.2 44 13 36 3 1.362 43 27 18 1.554 0.888 45 39 26 9.10 0.804 32.2 42 33 14 4 11.67 0.858 6.1 45 13 32 4
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.6 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 2,100.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-10 Cycle: 23 Core Average Exposure: MWd/MTU 18759.3 Exposure: MWd/MTU (GWd) 2101.0 ( 213.35 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.171 3.621 37 0.763 0.803 3 24 Inlet Subcooling: Btu/lbm -23.15 24 0.395 9.977 38 0.461 0.691 37 6 Flow: Mlb/hr 71.61 ( 93.00 %) 23 0.619 12.875 39 0.481 0.875 17 48 22 0.728 15.289 40 0.559 0.985 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.786 16.932 41 0.917 1.232 37 14 51 -- -- -- -- -- 51 20 0.816 18.146 42 1.157 1.423 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.829 18.825 43 1.240 1.471 25 26 43 -- -- -- -- 40 -- 40 -- -- -- -- 43 18 0.843 19.616 44 1.112 1.322 35 14 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.863 20.202 45 1.167 1.393 27 14 35 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 35 16 0.898 20.564 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.956 20.818 27 -- -- -- 8 -- 40 -- 40 -- 8 -- -- -- 27 14 0.993 20.935 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.087 21.063 19 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 19 12 1.146 21.820 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.196 22.326 11 -- -- -- -- 40 -- 40 -- -- -- -- 11 10 1.274 22.076 7 -- -- -- -- -- -- -- -- -- 7 9 1.317 22.452 3 -- -- -- -- -- 3 8 1.360 22.671 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.412 22.828 6 1.465 23.232 5 1.497* 23.234*
| |
| 4 1.477 22.580 Control Rod Density: % 6.57 3 1.425 21.139 2 1.142 16.448 k-effective: 1.00019 Bottom 1 0.307 4.725 Void Fraction: 0.511 Core Delta-P: psia 21.240 % AXIAL TILT -25.600 -10.947 Core Plate Delta-P: psia 16.684 AVG BOT 8ft/12ft 1.1449 1.0655 Coolant Temp: Deg-F 548.5 In Channel Flow: Mlb/hr 62.42 Active Channel Flow: Mlb/hr 60.13 Total Bypass Flow (%): 12.8 (of total core flow)
| |
| Total Water Rod Flow (%): 3.2 (of total core flow)
| |
| Source Convergence 0.00048 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.471 43 25 26 1.449 0.952 45 27 10 9.89 0.882 33.1 42 23 28 6 12.30 0.905 4.9 43 27 28 6 1.423 43 29 24 1.465 0.942 45 27 14 9.66 0.851 31.9 42 25 28 6 12.02 0.884 6.2 43 21 28 6 1.423 42 27 26 1.476 0.935 43 25 26 9.28 0.819 32.0 42 25 30 5 10.80 0.881 37.4 42 23 28 6 1.393 45 27 14 1.487 0.928 45 31 14 8.81 0.793 34.1 42 31 12 6 10.50 0.854 37.1 42 25 28 6 1.380 42 27 24 1.499 0.920 45 29 12 9.01 0.791 31.4 42 21 24 6 11.53 0.847 6.1 43 29 30 6 1.374 43 31 26 1.528 0.903 45 33 12 8.86 0.781 31.9 42 19 26 6 11.52 0.847 5.1 45 29 12 6 1.373 43 27 22 1.565 0.882 43 29 24 8.66 0.778 34.0 42 25 12 6 11.46 0.843 5.1 45 31 10 6 1.369 45 31 14 1.570 0.879 44 35 14 9.13 0.772 27.4 42 29 10 6 10.19 0.828 37.0 42 25 30 5 1.365 43 33 24 1.572 0.878 45 31 10 8.44 0.765 34.9 42 29 14 6 11.17 0.822 3.2 45 27 10 6 1.346 45 27 10 1.583 0.872 45 35 12 8.51 0.748 31.5 42 25 16 5 11.11 0.817 6.2 43 27 22 5
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.7 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 2,101.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-11 Cycle: 23 Core Average Exposure: MWd/MTU 19158.3 Exposure: MWd/MTU (GWd) 2500.0 ( 253.86 )
| |
| Delta E: MWd/MTU, (GWd) 399.0 ( 40.52 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.173 3.695 37 0.760 0.797 3 24 Inlet Subcooling: Btu/lbm -23.57 24 0.397 10.147 38 0.457 0.687 37 6 Flow: Mlb/hr 70.46 ( 91.50 %) 23 0.621 13.144 39 0.477 0.869 17 48 22 0.728 15.605 40 0.555 0.981 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.784 17.273 41 0.913 1.231 37 14 51 -- -- -- -- -- 51 20 0.811 18.499 42 1.155 1.411 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.823 19.184 43 1.245 1.469 25 26 43 -- -- -- -- 40 -- 40 -- -- -- -- 43 18 0.834 19.980 44 1.117 1.330 35 14 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.852 20.575 45 1.173 1.398 27 14 35 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 35 16 0.885 20.948 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.940 21.216 27 -- -- -- 8 -- 40 -- 40 -- 8 -- -- -- 27 14 0.976 21.348 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.069 21.478 19 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 19 12 1.128 22.258 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.180 22.783 11 -- -- -- -- 40 -- 40 -- -- -- -- 11 10 1.261 22.544 7 -- -- -- -- -- -- -- -- -- 7 9 1.311 22.936 3 -- -- -- -- -- 3 8 1.362 23.171 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.422 23.350 6 1.485 23.775 5 1.525* 23.790*
| |
| 4 1.509 23.130 Control Rod Density: % 6.57 3 1.450 21.668 2 1.161 16.871 k-effective: 1.00009 Bottom 1 0.314 4.848 Void Fraction: 0.515 Core Delta-P: psia 20.791 % AXIAL TILT -26.257 -11.117 Core Plate Delta-P: psia 16.235 AVG BOT 8ft/12ft 1.1465 1.0662 Coolant Temp: Deg-F 548.5 In Channel Flow: Mlb/hr 61.38 Active Channel Flow: Mlb/hr 59.11 Total Bypass Flow (%): 12.9 (of total core flow)
| |
| Total Water Rod Flow (%): 3.2 (of total core flow)
| |
| Source Convergence 0.00048 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.469 43 25 26 1.451 0.951 45 27 10 9.86 0.886 33.9 42 23 28 6 12.16 0.894 6.1 43 27 28 6 1.425 43 29 24 1.465 0.942 45 27 14 9.62 0.854 32.7 42 25 28 6 10.74 0.882 38.3 42 23 28 6 1.411 42 27 26 1.478 0.933 43 27 28 9.30 0.826 32.8 42 25 30 5 11.95 0.879 7.4 43 21 28 6 1.398 45 27 14 1.487 0.928 45 31 14 8.91 0.807 34.8 42 31 12 6 10.43 0.855 37.9 42 25 28 6 1.376 43 31 26 1.502 0.919 45 29 12 9.06 0.799 32.0 42 21 24 5 11.63 0.855 5.8 45 29 12 6 1.376 43 27 22 1.527 0.904 45 33 12 8.74 0.791 34.7 42 25 12 6 11.57 0.851 6.3 45 31 10 6 1.374 45 31 14 1.559 0.885 43 29 24 8.94 0.791 32.3 42 19 26 5 11.49 0.845 7.2 43 29 30 6 1.371 42 27 24 1.568 0.880 44 35 14 9.22 0.786 28.1 42 29 10 6 10.17 0.833 37.8 42 25 30 5 1.370 43 33 24 1.573 0.878 45 31 10 8.52 0.778 35.6 42 29 14 6 11.26 0.828 4.3 45 27 10 6 1.351 45 27 10 1.581 0.873 45 35 12 8.54 0.764 33.5 42 33 14 5 11.12 0.817 6.9 45 25 14 5
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.8 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 2,500.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-12 Cycle: 23 Core Average Exposure: MWd/MTU 19658.3 Exposure: MWd/MTU (GWd) 3000.0 ( 304.63 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.174 3.788 37 0.755 0.791 3 24 Inlet Subcooling: Btu/lbm -24.02 24 0.398 10.362 38 0.452 0.683 37 6 Flow: Mlb/hr 69.30 ( 90.00 %) 23 0.622 13.481 39 0.473 0.864 17 48 22 0.727 16.000 40 0.550 0.975 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.780 17.699 41 0.908 1.230 37 14 51 -- -- -- -- -- 51 20 0.804 18.939 42 1.151 1.397 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.813 19.629 43 1.249 1.467 25 26 43 -- -- -- -- 40 -- 40 -- -- -- -- 43 18 0.822 20.431 44 1.122 1.338 35 14 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.839 21.035 45 1.180 1.404 27 14 35 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 35 16 0.869 21.421 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.922 21.706 27 -- -- -- 8 -- 40 -- 40 -- 8 -- -- -- 27 14 0.956 21.856 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.048 21.989 19 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 19 12 1.108 22.797 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.162 23.348 11 -- -- -- -- 40 -- 40 -- -- -- -- 11 10 1.247 23.124 7 -- -- -- -- -- -- -- -- -- 7 9 1.306 23.539 3 -- -- -- -- -- 3 8 1.366 23.800 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.437 24.008 6 1.511 24.466 5 1.559* 24.500*
| |
| 4 1.545 23.834 Control Rod Density: % 6.57 3 1.478 22.343 2 1.182 17.411 k-effective: 0.99991 Bottom 1 0.321 5.006 Void Fraction: 0.519 Core Delta-P: psia 20.352 % AXIAL TILT -27.120 -11.340 Core Plate Delta-P: psia 15.798 AVG BOT 8ft/12ft 1.1491 1.0671 Coolant Temp: Deg-F 548.5 In Channel Flow: Mlb/hr 60.33 Active Channel Flow: Mlb/hr 58.09 Total Bypass Flow (%): 12.9 (of total core flow)
| |
| Total Water Rod Flow (%): 3.2 (of total core flow)
| |
| Source Convergence 0.00038 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.467 43 25 26 1.457 0.947 45 27 10 9.82 0.890 35.0 42 23 28 6 12.03 0.884 7.6 43 27 28 6 1.425 43 29 24 1.467 0.940 45 27 14 9.56 0.857 33.7 42 25 28 6 10.65 0.883 39.4 42 23 28 6 1.404 45 27 14 1.484 0.930 43 27 28 9.31 0.835 33.8 42 25 30 5 11.85 0.871 8.9 43 21 28 6 1.397 42 27 26 1.488 0.927 45 31 14 9.03 0.825 35.8 42 31 12 6 11.77 0.865 7.3 45 29 12 6 1.382 45 31 14 1.506 0.916 45 29 12 9.11 0.811 33.0 42 21 24 5 11.68 0.859 7.8 45 31 10 6 1.378 43 27 22 1.526 0.904 45 33 12 8.85 0.807 35.6 42 25 12 6 10.35 0.856 39.0 42 25 28 6 1.377 43 31 26 1.555 0.887 43 29 24 9.36 0.804 29.1 42 29 10 6 11.42 0.840 8.7 43 29 30 6 1.374 43 33 24 1.565 0.882 44 35 14 9.00 0.803 33.2 42 19 26 5 11.40 0.838 5.8 45 27 10 6 1.360 42 27 24 1.574 0.877 45 31 10 8.62 0.793 36.5 42 29 14 6 10.15 0.838 38.9 42 25 30 5 1.358 45 27 10 1.578 0.874 45 35 12 8.68 0.783 34.5 42 33 14 5 11.19 0.823 8.2 45 25 14 4
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.9 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 3,000.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-13 Cycle: 23 Core Average Exposure: MWd/MTU 20158.2 Exposure: MWd/MTU (GWd) 3500.0 ( 355.41 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.175 3.881 37 0.751 0.785 3 24 Inlet Subcooling: Btu/lbm -24.47 24 0.401 10.577 38 0.448 0.679 37 6 Flow: Mlb/hr 68.14 ( 88.50 %) 23 0.625 13.820 39 0.470 0.859 17 48 22 0.728 16.395 40 0.545 0.969 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.778 18.123 41 0.903 1.228 37 14 51 -- -- -- -- -- 51 20 0.800 19.375 42 1.147 1.383 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.807 20.070 43 1.254 1.464 25 26 43 -- -- -- -- 40 -- 40 -- -- -- -- 43 18 0.814 20.877 44 1.128 1.346 35 14 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.828 21.489 45 1.187 1.409 27 14 35 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 35 16 0.856 21.886 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.907 22.187 27 -- -- -- 8 -- 40 -- 40 -- 8 -- -- -- 27 14 0.940 22.354 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.031 22.491 19 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 19 12 1.092 23.328 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.148 23.905 11 -- -- -- -- 40 -- 40 -- -- -- -- 11 10 1.236 23.699 7 -- -- -- -- -- -- -- -- -- 7 9 1.303 24.140 3 -- -- -- -- -- 3 8 1.370 24.431 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.448 24.673 6 1.531 25.167 5 1.585* 25.225*
| |
| 4 1.573 24.553 Control Rod Density: % 6.57 3 1.500 23.029 2 1.198 17.959 k-effective: 0.99967 Bottom 1 0.328 5.166 Void Fraction: 0.523 Core Delta-P: psia 19.908 % AXIAL TILT -27.758 -11.571 Core Plate Delta-P: psia 15.355 AVG BOT 8ft/12ft 1.1508 1.0681 Coolant Temp: Deg-F 548.5 In Channel Flow: Mlb/hr 59.29 Active Channel Flow: Mlb/hr 57.07 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00039 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.464 43 25 26 1.456 0.948 45 27 10 9.74 0.892 36.0 42 23 28 6 10.52 0.881 40.5 42 23 28 6 1.425 43 29 24 1.468 0.940 45 27 14 9.48 0.857 34.7 42 25 28 6 11.87 0.873 9.1 43 27 28 5 1.409 45 27 14 1.480 0.932 43 27 28 9.10 0.839 36.7 42 31 12 6 11.84 0.870 8.8 45 29 12 6 1.388 45 31 14 1.489 0.927 45 31 14 9.27 0.839 34.8 42 25 30 5 11.73 0.863 9.2 45 31 10 6 1.383 42 27 26 1.509 0.914 45 29 12 8.93 0.822 36.5 42 25 12 6 11.69 0.860 10.4 43 21 28 6 1.380 43 27 22 1.525 0.905 45 33 12 9.45 0.820 30.1 42 29 10 6 10.24 0.855 40.1 42 25 28 6 1.379 43 31 26 1.549 0.891 43 29 24 9.12 0.819 33.9 42 21 24 5 11.50 0.846 5.6 45 27 10 5 1.378 43 33 24 1.554 0.888 44 35 14 9.02 0.812 34.2 42 19 26 5 10.07 0.839 39.9 42 25 30 5 1.367 45 27 10 1.574 0.877 45 31 10 8.67 0.805 37.4 42 29 14 6 10.04 0.833 39.5 42 31 12 6 1.360 45 33 12 1.576 0.876 45 35 12 8.76 0.798 35.4 42 33 14 5 11.30 0.831 10.1 43 29 30 6
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.10 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 3,500.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-14 Cycle: 23 Core Average Exposure: MWd/MTU 20658.3 Exposure: MWd/MTU (GWd) 4000.0 ( 406.18 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.177 3.976 37 0.747 0.780 3 24 Inlet Subcooling: Btu/lbm -24.78 24 0.403 10.793 38 0.445 0.676 37 6 Flow: Mlb/hr 67.38 ( 87.50 %) 23 0.628 14.160 39 0.466 0.854 17 48 22 0.730 16.791 40 0.541 0.964 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.778 18.546 41 0.899 1.227 37 14 51 -- -- -- -- -- 51 20 0.797 19.810 42 1.144 1.370 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.803 20.508 43 1.258 1.462 25 26 43 -- -- -- -- 40 -- 40 -- -- -- -- 43 18 0.808 21.318 44 1.134 1.352 35 14 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.821 21.938 45 1.193 1.414 27 14 35 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 35 16 0.847 22.345 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.896 22.661 27 -- -- -- 8 -- 40 -- 40 -- 8 -- -- -- 27 14 0.929 22.846 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.020 22.986 19 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 19 12 1.081 23.852 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.139 24.457 11 -- -- -- -- 40 -- 40 -- -- -- -- 11 10 1.229 24.270 7 -- -- -- -- -- -- -- -- -- 7 9 1.301 24.741 3 -- -- -- -- -- 3 8 1.374 25.063 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.457 25.343 6 1.545 25.876 5 1.601* 25.960*
| |
| 4 1.589 25.282 Control Rod Density: % 6.57 3 1.511 23.723 2 1.204 18.512 k-effective: 0.99949 Bottom 1 0.331 5.330 Void Fraction: 0.526 Core Delta-P: psia 19.610 % AXIAL TILT -28.128 -11.804 Core Plate Delta-P: psia 15.057 AVG BOT 8ft/12ft 1.1514 1.0690 Coolant Temp: Deg-F 548.4 In Channel Flow: Mlb/hr 58.60 Active Channel Flow: Mlb/hr 56.40 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00029 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.462 43 25 26 1.456 0.948 45 27 10 9.64 0.891 37.0 42 23 28 6 10.38 0.877 41.6 42 23 28 6 1.426 43 29 24 1.471 0.938 45 27 14 9.40 0.857 35.5 42 25 28 5 11.86 0.872 10.3 45 29 12 6 1.414 45 27 14 1.480 0.933 43 27 28 9.13 0.850 37.7 42 31 12 6 11.70 0.861 10.7 45 31 10 6 1.393 45 31 14 1.492 0.925 45 31 14 9.20 0.841 35.7 42 25 30 5 11.68 0.859 10.6 43 27 28 5 1.382 43 33 24 1.515 0.911 45 29 12 8.97 0.833 37.5 42 25 12 6 10.12 0.852 41.2 42 25 28 6 1.381 43 27 22 1.526 0.904 45 33 12 9.50 0.831 31.1 42 29 10 6 11.56 0.850 7.1 45 27 10 5 1.381 43 31 26 1.546 0.893 43 29 24 9.10 0.824 34.9 42 21 24 5 11.55 0.849 11.3 43 21 26 6 1.374 45 27 10 1.547 0.892 44 35 14 9.00 0.817 35.1 42 19 26 5 10.06 0.842 40.5 42 31 12 6 1.370 42 27 26 1.575 0.876 45 31 10 8.69 0.814 38.3 42 29 14 6 9.96 0.837 41.0 42 25 30 5 1.367 45 33 12 1.575 0.876 45 35 12 8.80 0.808 36.3 42 33 14 5 10.60 0.832 32.6 42 29 10 6
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.11 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 4,000.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-15 Cycle: 23 Core Average Exposure: MWd/MTU 21058.3 Exposure: MWd/MTU (GWd) 4400.0 ( 446.80 )
| |
| Delta E: MWd/MTU, (GWd) 400.0 ( 40.62 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.179 4.052 37 0.744 0.776 3 24 Inlet Subcooling: Btu/lbm -24.79 24 0.407 10.967 38 0.441 0.673 37 6 Flow: Mlb/hr 67.38 ( 87.50 %) 23 0.634 14.433 39 0.463 0.850 17 48 22 0.736 17.109 40 0.537 0.960 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.782 18.886 41 0.896 1.226 37 14 51 -- -- -- -- -- 51 20 0.800 20.158 42 1.142 1.362 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.803 20.858 43 1.262 1.461 25 26 43 -- -- -- -- 40 -- 40 -- -- -- -- 43 18 0.807 21.670 44 1.137 1.357 35 14 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.819 22.295 45 1.198 1.417 27 14 35 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 35 16 0.844 22.710 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.891 23.037 27 -- -- -- 8 -- 40 -- 40 -- 8 -- -- -- 27 14 0.923 23.236 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.013 23.378 19 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 19 12 1.075 24.268 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.134 24.895 11 -- -- -- -- 40 -- 40 -- -- -- -- 11 10 1.225 24.724 7 -- -- -- -- -- -- -- -- -- 7 9 1.300 25.220 3 -- -- -- -- -- 3 8 1.375 25.570 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.460 25.881 6 1.549 26.446 5 1.606* 26.551*
| |
| 4 1.593 25.869 Control Rod Density: % 6.57 3 1.511 24.280 2 1.202 18.955 k-effective: 0.99949 Bottom 1 0.331 5.461 Void Fraction: 0.525 Core Delta-P: psia 19.608 % AXIAL TILT -28.088 -11.986 Core Plate Delta-P: psia 15.056 AVG BOT 8ft/12ft 1.1503 1.0697 Coolant Temp: Deg-F 548.4 In Channel Flow: Mlb/hr 58.60 Active Channel Flow: Mlb/hr 56.40 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00028 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.461 43 25 26 1.462 0.944 45 27 10 9.55 0.890 37.8 42 23 28 6 10.26 0.873 42.5 42 23 28 6 1.427 43 29 24 1.480 0.933 45 27 14 9.13 0.856 38.5 42 31 12 6 11.83 0.870 11.5 45 29 12 6 1.417 45 27 14 1.485 0.929 43 27 28 9.31 0.855 36.3 42 25 28 5 11.63 0.855 11.8 45 31 10 6 1.397 45 31 14 1.500 0.920 45 31 14 9.13 0.840 36.5 42 25 30 5 10.01 0.849 42.0 42 25 28 6 1.386 43 33 24 1.524 0.905 45 29 12 8.97 0.839 38.2 42 25 12 6 11.53 0.848 8.2 45 27 10 5 1.384 43 27 22 1.533 0.900 45 33 12 9.50 0.838 31.9 42 29 10 6 10.05 0.847 41.4 42 31 12 6 1.383 43 31 26 1.547 0.892 44 35 14 9.05 0.826 35.7 42 21 24 5 11.51 0.846 11.8 43 27 28 5 1.380 45 27 10 1.548 0.891 43 29 24 8.96 0.820 35.9 42 19 26 5 11.45 0.842 12.5 43 21 26 6 1.372 45 33 12 1.580 0.873 45 31 10 8.68 0.819 39.1 42 29 14 6 10.52 0.837 34.2 42 29 10 6 1.369 45 29 12 1.580 0.873 45 35 12 8.80 0.814 37.0 42 33 14 5 9.85 0.834 41.8 42 25 30 5
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.12 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 4,400.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-16 Cycle: 23 Core Average Exposure: MWd/MTU 21458.3 Exposure: MWd/MTU (GWd) 4800.0 ( 487.42 )
| |
| Delta E: MWd/MTU, (GWd) 400.0 ( 40.62 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.181 4.129 37 0.741 0.771 3 24 Inlet Subcooling: Btu/lbm -24.79 24 0.411 11.143 38 0.438 0.670 37 6 Flow: Mlb/hr 67.38 ( 87.50 %) 23 0.640 14.710 39 0.460 0.846 17 48 22 0.742 17.430 40 0.534 0.956 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.787 19.228 41 0.893 1.225 37 14 51 -- -- -- -- -- 51 20 0.803 20.507 42 1.140 1.354 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.806 21.208 43 1.266 1.461 25 26 43 -- -- -- -- 40 -- 40 -- -- -- -- 43 18 0.808 22.022 44 1.141 1.362 35 14 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.818 22.651 45 1.202 1.420 27 14 35 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 35 16 0.842 23.074 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.888 23.411 27 -- -- -- 8 -- 40 -- 40 -- 8 -- -- -- 27 14 0.920 23.624 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.009 23.768 19 -- -- -- 12 -- 8 -- 8 -- 12 -- -- -- 19 12 1.071 24.682 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.130 25.332 11 -- -- -- -- 40 -- 40 -- -- -- -- 11 10 1.222 25.177 7 -- -- -- -- -- -- -- -- -- 7 9 1.299 25.699 3 -- -- -- -- -- 3 8 1.375 26.078 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.461 26.420 6 1.551 27.018 5 1.607* 27.143*
| |
| 4 1.593 26.456 Control Rod Density: % 6.57 3 1.508 24.836 2 1.197 19.397 k-effective: 0.99946 Bottom 1 0.331 5.592 Void Fraction: 0.524 Core Delta-P: psia 19.602 % AXIAL TILT -27.915 -12.159 Core Plate Delta-P: psia 15.049 AVG BOT 8ft/12ft 1.1485 1.0703 Coolant Temp: Deg-F 548.4 In Channel Flow: Mlb/hr 58.61 Active Channel Flow: Mlb/hr 56.41 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00030 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.461 43 25 26 1.468 0.940 45 27 10 9.46 0.888 38.6 42 23 28 6 10.13 0.869 43.3 42 23 28 6 1.429 43 29 24 1.488 0.927 45 27 14 9.10 0.860 39.2 42 31 12 6 11.77 0.865 12.7 45 29 12 6 1.420 45 27 14 1.489 0.927 43 27 28 9.21 0.852 37.1 42 25 28 5 10.01 0.850 42.2 42 31 12 6 1.400 45 31 14 1.507 0.916 45 31 14 8.94 0.843 39.0 42 25 12 6 11.54 0.849 13.0 45 31 10 6 1.390 43 33 24 1.533 0.900 45 29 12 9.48 0.842 32.7 42 29 10 6 9.89 0.845 42.9 42 25 28 6 1.387 43 31 26 1.539 0.897 45 33 12 9.05 0.838 37.3 42 25 30 5 11.46 0.843 9.4 45 27 10 5 1.386 43 27 22 1.546 0.893 44 35 14 9.00 0.827 36.4 42 21 24 5 10.49 0.840 35.1 42 29 10 6 1.384 45 27 10 1.549 0.891 43 29 24 8.66 0.822 39.8 42 29 14 6 11.36 0.835 13.6 43 21 26 6 1.376 45 33 12 1.585 0.871 45 35 12 8.92 0.822 36.6 42 19 26 5 11.33 0.833 12.9 43 27 28 5 1.373 45 29 12 1.585 0.870 45 31 10 8.78 0.818 37.8 42 33 14 5 9.73 0.830 42.6 42 25 30 5
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.13 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 4,800.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-17 Cycle: 23 Core Average Exposure: MWd/MTU 21459.3 Exposure: MWd/MTU (GWd) 4801.0 ( 487.52 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.162 4.129 37 0.742 0.775 3 24 Inlet Subcooling: Btu/lbm -23.87 24 0.368 11.144 38 0.434 0.662 47 16 Flow: Mlb/hr 69.68 ( 90.50 %) 23 0.572 14.711 39 0.454 0.815 17 48 22 0.662 17.431 40 0.527 0.966 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.700 19.228 41 0.891 1.232 39 38 51 -- -- -- -- -- 51 20 0.735 20.507 42 1.139 1.346 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.760 21.209 43 1.297 1.465 25 26 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.790 22.023 44 1.161 1.352 39 36 39 -- -- 42 -- 6 -- 6 -- 42 -- -- 39 17 0.819 22.652 45 1.175 1.302 41 18 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 0.854 23.075 31 -- -- -- 0 -- 20 -- 40 -- 6 -- -- -- 31 15 0.904 23.412 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 0.932 23.625 23 -- -- -- 6 -- 40 -- 20 -- 6 -- -- -- 23 13 1.020 23.769 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.080 24.683 15 -- -- 42 -- 6 -- 6 -- 42 -- -- 15 11 1.140 25.333 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.233 25.178 7 -- -- -- -- -- -- -- -- -- 7 9 1.312 25.701 3 -- -- -- -- -- 3 8 1.392 26.079 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.484 26.421 6 1.583 27.020 5 1.656 27.145*
| |
| 4 1.666* 26.458 Control Rod Density: % 6.66 3 1.576 24.837 2 1.254 19.398 k-effective: 0.99967 Bottom 1 0.347 5.592 Void Fraction: 0.526 Core Delta-P: psia 20.671 % AXIAL TILT -31.128 -12.159 Core Plate Delta-P: psia 16.115 AVG BOT 8ft/12ft 1.1735 1.0703 Coolant Temp: Deg-F 548.5 In Channel Flow: Mlb/hr 60.61 Active Channel Flow: Mlb/hr 58.34 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00045 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.465 43 25 26 1.483 0.931 43 27 28 9.50 0.896 39.0 41 13 16 5 11.98 0.881 12.7 44 39 40 5 1.445 43 25 22 1.518 0.909 44 39 36 9.51 0.894 38.7 41 37 40 5 10.65 0.880 39.0 42 21 24 6 1.444 43 31 28 1.535 0.899 43 25 22 9.67 0.889 36.4 42 23 22 6 10.66 0.880 38.8 42 23 22 6 1.429 43 23 20 1.539 0.897 43 23 20 9.65 0.889 36.5 42 21 24 6 11.93 0.877 10.1 44 39 36 5 1.424 43 33 30 1.540 0.896 43 31 28 9.48 0.854 34.3 42 37 36 5 10.08 0.874 44.7 41 13 16 5 1.422 43 19 20 1.562 0.883 43 29 30 9.39 0.852 35.1 42 21 20 5 10.05 0.869 44.3 41 37 14 5 1.420 43 23 24 1.577 0.875 43 19 24 9.34 0.852 35.6 42 19 22 5 11.77 0.865 11.5 43 37 38 5 1.403 43 21 22 1.578 0.875 44 35 40 9.33 0.852 35.7 42 17 16 5 11.65 0.856 10.6 43 15 20 4 1.401 43 35 36 1.586 0.870 43 19 20 9.35 0.845 34.6 42 17 20 4 11.61 0.854 13.2 43 21 22 6 1.354 43 35 28 1.596 0.865 43 35 36 9.32 0.842 34.6 42 19 18 4 11.60 0.853 10.6 43 35 36 4
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.14 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 4,801.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-18 Cycle: 23 Core Average Exposure: MWd/MTU 21908.3 Exposure: MWd/MTU (GWd) 5250.0 ( 533.11 )
| |
| Delta E: MWd/MTU, (GWd) 449.0 ( 45.59 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.164 4.208 37 0.739 0.770 3 24 Inlet Subcooling: Btu/lbm -23.87 24 0.372 11.323 38 0.431 0.659 47 16 Flow: Mlb/hr 69.68 ( 90.50 %) 23 0.579 14.991 39 0.451 0.811 17 48 22 0.670 17.755 40 0.524 0.960 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.706 19.572 41 0.887 1.229 39 38 51 -- -- -- -- -- 51 20 0.740 20.868 42 1.137 1.340 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.763 21.581 43 1.302 1.467 25 26 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.793 22.410 44 1.164 1.356 39 36 39 -- -- 42 -- 6 -- 6 -- 42 -- -- 39 17 0.820 23.053 45 1.180 1.307 41 18 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 0.854 23.488 31 -- -- -- 0 -- 20 -- 40 -- 6 -- -- -- 31 15 0.904 23.839 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 0.930 24.065 23 -- -- -- 6 -- 40 -- 20 -- 6 -- -- -- 23 13 1.018 24.211 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.078 25.151 15 -- -- 42 -- 6 -- 6 -- 42 -- -- 15 11 1.137 25.826 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.230 25.690 7 -- -- -- -- -- -- -- -- -- 7 9 1.310 26.243 3 -- -- -- -- -- 3 8 1.391 26.655 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.483 27.035 6 1.582 27.675 5 1.653 27.830*
| |
| 4 1.662* 27.147 Control Rod Density: % 6.66 3 1.569 25.488 2 1.246 19.915 k-effective: 0.99957 Bottom 1 0.346 5.747 Void Fraction: 0.525 Core Delta-P: psia 20.659 % AXIAL TILT -30.824 -12.409 Core Plate Delta-P: psia 16.103 AVG BOT 8ft/12ft 1.1713 1.0715 Coolant Temp: Deg-F 548.5 In Channel Flow: Mlb/hr 60.62 Active Channel Flow: Mlb/hr 58.35 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00047 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.467 43 25 26 1.485 0.929 43 27 28 9.44 0.897 39.8 41 13 16 5 10.56 0.880 40.0 42 21 24 6 1.450 43 25 22 1.534 0.899 43 25 22 9.45 0.896 39.6 41 37 40 5 10.57 0.879 39.8 42 23 22 6 1.450 43 31 28 1.536 0.899 44 39 36 9.58 0.890 37.4 42 21 24 6 9.98 0.873 45.6 41 13 16 5 1.433 43 23 20 1.539 0.897 43 31 28 9.59 0.889 37.3 42 23 22 6 11.85 0.871 13.7 44 39 40 5 1.430 43 33 30 1.540 0.896 43 23 20 9.41 0.856 35.2 42 37 36 5 11.84 0.871 11.5 44 39 36 5 1.426 43 19 20 1.561 0.884 43 29 30 9.28 0.854 36.6 42 17 16 5 9.96 0.868 45.2 41 37 14 5 1.425 43 23 24 1.578 0.875 43 19 24 9.27 0.854 36.5 42 19 22 5 11.62 0.855 12.8 43 37 38 5 1.409 43 21 22 1.584 0.871 44 35 14 9.31 0.853 36.0 42 21 20 5 10.04 0.851 42.0 42 35 38 5 1.405 43 35 36 1.600 0.862 43 19 20 9.28 0.846 35.5 42 17 20 4 10.06 0.848 41.3 42 37 36 5 1.360 43 35 28 1.607 0.859 43 21 22 9.25 0.843 35.5 42 19 18 4 11.50 0.846 14.3 44 35 40 5
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.15 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 5,250.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-19 Cycle: 23 Core Average Exposure: MWd/MTU 22358.3 Exposure: MWd/MTU (GWd) 5700.0 ( 578.81 )
| |
| Delta E: MWd/MTU, (GWd) 450.0 ( 45.70 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.166 4.287 37 0.735 0.765 3 24 Inlet Subcooling: Btu/lbm -23.79 24 0.375 11.504 38 0.427 0.655 47 16 Flow: Mlb/hr 69.88 ( 90.75 %) 23 0.584 15.275 39 0.448 0.807 17 48 22 0.675 18.084 40 0.519 0.955 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.710 19.919 41 0.883 1.227 39 38 51 -- -- -- -- -- 51 20 0.743 21.231 42 1.135 1.333 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.766 21.956 43 1.307 1.469 25 26 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.795 22.799 44 1.168 1.360 39 36 39 -- -- 42 -- 6 -- 6 -- 42 -- -- 39 17 0.822 23.455 45 1.184 1.312 41 18 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 0.855 23.903 31 -- -- -- 0 -- 20 -- 40 -- 6 -- -- -- 31 15 0.904 24.267 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 0.930 24.505 23 -- -- -- 6 -- 40 -- 20 -- 6 -- -- -- 23 13 1.018 24.653 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.078 25.619 15 -- -- 42 -- 6 -- 6 -- 42 -- -- 15 11 1.137 26.320 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.229 26.202 7 -- -- -- -- -- -- -- -- -- 7 9 1.309 26.787 3 -- -- -- -- -- 3 8 1.390 27.232 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.482 27.650 6 1.581 28.331 5 1.651 28.516*
| |
| 4 1.658* 27.835 Control Rod Density: % 6.66 3 1.563 26.138 2 1.238 20.430 k-effective: 0.99957 Bottom 1 0.344 5.901 Void Fraction: 0.523 Core Delta-P: psia 20.728 % AXIAL TILT -30.589 -12.643 Core Plate Delta-P: psia 16.173 AVG BOT 8ft/12ft 1.1696 1.0725 Coolant Temp: Deg-F 548.5 In Channel Flow: Mlb/hr 60.80 Active Channel Flow: Mlb/hr 58.52 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00023 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.469 43 25 26 1.490 0.926 43 27 28 9.39 0.901 40.7 41 13 16 5 10.49 0.882 41.0 42 21 24 6 1.455 43 25 22 1.536 0.898 43 25 22 9.40 0.900 40.5 41 37 40 5 10.49 0.880 40.8 42 23 22 6 1.455 43 31 28 1.541 0.896 43 31 28 9.52 0.892 38.3 42 21 24 6 9.90 0.873 46.6 41 13 16 5 1.437 43 23 20 1.546 0.893 44 39 36 9.52 0.891 38.2 42 23 22 6 9.88 0.868 46.2 41 37 14 5 1.436 43 33 30 1.549 0.891 43 23 20 9.37 0.859 36.1 42 37 36 5 11.78 0.866 15.1 44 39 40 5 1.431 43 19 20 1.561 0.884 43 29 30 9.24 0.858 37.4 42 17 16 5 11.76 0.864 12.9 44 39 36 5 1.430 43 23 24 1.578 0.875 43 33 30 9.23 0.857 37.4 42 19 22 5 9.99 0.854 42.9 42 35 38 5 1.415 43 21 22 1.590 0.868 44 35 14 9.26 0.855 36.9 42 21 20 5 10.01 0.850 42.3 42 37 36 5 1.410 43 35 36 1.601 0.862 43 19 20 9.23 0.848 36.4 42 17 20 4 11.52 0.847 14.3 43 37 38 5 1.366 43 35 28 1.606 0.859 43 21 22 9.20 0.845 36.4 42 19 18 4 9.82 0.845 43.7 42 19 22 6
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.16 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 5,700.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-20 Cycle: 23 Core Average Exposure: MWd/MTU 22858.3 Exposure: MWd/MTU (GWd) 6200.0 ( 629.58 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.168 4.377 37 0.731 0.759 3 24 Inlet Subcooling: Btu/lbm -23.72 24 0.380 11.707 38 0.423 0.651 47 16 Flow: Mlb/hr 70.07 ( 91.00 %) 23 0.593 15.595 39 0.444 0.803 17 48 22 0.684 18.452 40 0.515 0.949 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.718 20.307 41 0.879 1.224 39 38 51 -- -- -- -- -- 51 20 0.750 21.637 42 1.133 1.326 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.771 22.374 43 1.313 1.472 25 26 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.799 23.232 44 1.171 1.365 39 36 39 -- -- 42 -- 6 -- 6 -- 42 -- -- 39 17 0.825 23.904 45 1.188 1.317 41 18 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 0.856 24.364 31 -- -- -- 0 -- 20 -- 40 -- 6 -- -- -- 31 15 0.904 24.742 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 0.929 24.994 23 -- -- -- 6 -- 40 -- 20 -- 6 -- -- -- 23 13 1.016 25.143 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.076 26.139 15 -- -- 42 -- 6 -- 6 -- 42 -- -- 15 11 1.134 26.868 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.224 26.770 7 -- -- -- -- -- -- -- -- -- 7 9 1.304 27.389 3 -- -- -- -- -- 3 8 1.385 27.871 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.477 28.332 6 1.576 29.059 5 1.647 29.276*
| |
| 4 1.653* 28.599 Control Rod Density: % 6.66 3 1.557 26.857 2 1.231 20.998 k-effective: 0.99957 Bottom 1 0.343 6.071 Void Fraction: 0.521 Core Delta-P: psia 20.792 % AXIAL TILT -30.139 -12.885 Core Plate Delta-P: psia 16.236 AVG BOT 8ft/12ft 1.1666 1.0736 Coolant Temp: Deg-F 548.5 In Channel Flow: Mlb/hr 60.98 Active Channel Flow: Mlb/hr 58.70 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.2 (of total core flow)
| |
| Source Convergence 0.00049 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.472 43 25 26 1.493 0.924 43 27 28 9.33 0.903 41.7 41 13 16 5 10.41 0.883 42.1 42 21 24 6 1.462 43 31 28 1.536 0.899 43 25 22 9.34 0.902 41.5 41 37 40 5 10.40 0.881 41.9 42 23 22 6 1.462 43 25 22 1.539 0.897 43 31 28 9.45 0.894 39.3 42 21 24 6 9.80 0.872 47.6 41 13 16 5 1.444 43 33 30 1.552 0.889 43 23 20 9.45 0.892 39.2 42 23 22 6 10.04 0.868 44.4 41 37 40 5 1.443 43 23 20 1.555 0.887 44 39 36 9.31 0.861 37.1 42 37 36 5 11.70 0.860 16.6 44 39 40 5 1.438 43 23 24 1.559 0.885 43 29 30 9.19 0.861 38.4 42 17 16 5 11.64 0.856 14.3 44 39 36 5 1.437 43 19 20 1.574 0.877 43 33 30 9.18 0.860 38.4 42 19 22 5 9.92 0.855 44.0 42 35 38 5 1.422 43 21 22 1.597 0.864 44 35 14 9.20 0.857 37.9 42 21 20 5 9.93 0.851 43.3 42 37 36 5 1.417 43 35 36 1.602 0.861 43 19 20 9.17 0.850 37.4 42 17 20 4 9.75 0.846 44.7 42 19 22 6 1.374 43 35 28 1.603 0.861 43 21 22 9.14 0.848 37.3 42 19 18 4 9.75 0.844 44.5 42 21 20 6
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.17 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 6,200.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-21 Cycle: 23 Core Average Exposure: MWd/MTU 23358.3 Exposure: MWd/MTU (GWd) 6700.0 ( 680.35 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.170 4.467 37 0.727 0.754 3 24 Inlet Subcooling: Btu/lbm -23.65 24 0.385 11.913 38 0.419 0.647 47 16 Flow: Mlb/hr 70.26 ( 91.25 %) 23 0.600 15.918 39 0.440 0.797 17 48 22 0.692 18.826 40 0.510 0.943 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.724 20.700 41 0.875 1.222 39 38 51 -- -- -- -- -- 51 20 0.756 22.047 42 1.132 1.320 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.776 22.795 43 1.320 1.476 25 26 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.803 23.669 44 1.174 1.370 39 36 39 -- -- 42 -- 6 -- 6 -- 42 -- -- 39 17 0.828 24.354 45 1.192 1.323 41 18 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 0.858 24.827 31 -- -- -- 0 -- 20 -- 40 -- 6 -- -- -- 31 15 0.904 25.218 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 0.929 25.483 23 -- -- -- 6 -- 40 -- 20 -- 6 -- -- -- 23 13 1.015 25.633 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.074 26.657 15 -- -- 42 -- 6 -- 6 -- 42 -- -- 15 11 1.131 27.414 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.220 27.336 7 -- -- -- -- -- -- -- -- -- 7 9 1.299 27.989 3 -- -- -- -- -- 3 8 1.379 28.508 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.471 29.012 6 1.570 29.784 5 1.642 30.034*
| |
| 4 1.650* 29.360 Control Rod Density: % 6.66 3 1.554 27.574 2 1.227 21.564 k-effective: 0.99959 Bottom 1 0.342 6.241 Void Fraction: 0.519 Core Delta-P: psia 20.857 % AXIAL TILT -29.741 -13.107 Core Plate Delta-P: psia 16.302 AVG BOT 8ft/12ft 1.1638 1.0746 Coolant Temp: Deg-F 548.5 In Channel Flow: Mlb/hr 61.16 Active Channel Flow: Mlb/hr 58.88 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.2 (of total core flow)
| |
| Source Convergence 0.00047 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.476 43 25 26 1.495 0.923 43 27 28 9.27 0.906 42.7 41 13 16 5 10.33 0.884 43.2 42 21 24 6 1.470 43 31 28 1.534 0.900 43 25 22 9.28 0.905 42.5 41 37 40 5 10.32 0.882 43.0 42 23 22 6 1.470 43 25 22 1.537 0.898 43 31 28 9.38 0.896 40.3 42 21 24 6 9.98 0.872 45.6 41 13 16 5 1.453 43 33 30 1.557 0.886 43 29 30 9.38 0.894 40.2 42 23 22 6 9.96 0.870 45.4 41 37 40 5 1.450 43 23 20 1.560 0.885 43 23 20 9.15 0.865 39.4 42 17 16 5 9.86 0.857 45.0 42 35 38 5 1.445 43 23 24 1.564 0.882 44 39 36 9.26 0.865 38.0 42 37 36 5 11.62 0.854 18.0 44 39 40 5 1.445 43 19 20 1.570 0.879 43 33 30 9.13 0.864 39.3 42 19 22 5 9.87 0.853 44.3 42 37 36 5 1.431 43 21 22 1.599 0.863 43 21 22 9.14 0.860 38.8 42 21 20 5 11.54 0.849 15.8 44 39 36 5 1.424 43 35 36 1.600 0.863 44 35 14 9.12 0.854 38.3 42 17 20 4 9.69 0.848 45.7 42 19 22 6 1.382 43 35 28 1.602 0.862 43 19 20 9.09 0.851 38.3 42 19 18 4 9.67 0.845 45.5 42 21 20 6
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.18 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 6,700.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-22 Cycle: 23 Core Average Exposure: MWd/MTU 23758.2 Exposure: MWd/MTU (GWd) 7100.0 ( 720.97 )
| |
| Delta E: MWd/MTU, (GWd) 400.0 ( 40.62 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.172 4.541 37 0.723 0.749 3 24 Inlet Subcooling: Btu/lbm -23.72 24 0.388 12.080 38 0.416 0.644 47 16 Flow: Mlb/hr 70.07 ( 91.00 %) 23 0.606 16.180 39 0.437 0.794 17 48 22 0.698 19.128 40 0.507 0.938 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.729 21.016 41 0.871 1.220 39 38 51 -- -- -- -- -- 51 20 0.760 22.377 42 1.130 1.316 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.780 23.135 43 1.326 1.480 25 26 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.807 24.019 44 1.176 1.374 39 36 39 -- -- 42 -- 6 -- 6 -- 42 -- -- 39 17 0.831 24.715 45 1.196 1.328 41 18 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 0.859 25.197 31 -- -- -- 0 -- 20 -- 40 -- 6 -- -- -- 31 15 0.904 25.598 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 0.928 25.873 23 -- -- -- 6 -- 40 -- 20 -- 6 -- -- -- 23 13 1.013 26.025 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.071 27.071 15 -- -- 42 -- 6 -- 6 -- 42 -- -- 15 11 1.128 27.850 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.215 27.786 7 -- -- -- -- -- -- -- -- -- 7 9 1.293 28.467 3 -- -- -- -- -- 3 8 1.373 29.015 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.465 29.553 6 1.565 30.362 5 1.640 30.639*
| |
| 4 1.650* 29.969 Control Rod Density: % 6.66 3 1.556 28.147 2 1.228 22.017 k-effective: 0.99953 Bottom 1 0.343 6.377 Void Fraction: 0.519 Core Delta-P: psia 20.766 % AXIAL TILT -29.451 -13.272 Core Plate Delta-P: psia 16.211 AVG BOT 8ft/12ft 1.1618 1.0753 Coolant Temp: Deg-F 548.5 In Channel Flow: Mlb/hr 60.99 Active Channel Flow: Mlb/hr 58.72 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.2 (of total core flow)
| |
| Source Convergence 0.00043 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.480 43 25 26 1.492 0.925 43 27 28 9.22 0.909 43.5 41 13 16 5 10.24 0.883 44.0 42 21 24 6 1.476 43 31 28 1.529 0.903 43 25 22 9.23 0.908 43.3 41 37 40 5 10.23 0.881 43.8 42 23 22 6 1.476 43 25 22 1.532 0.901 43 31 28 9.31 0.897 41.1 42 21 24 6 9.92 0.873 46.4 41 13 16 5 1.460 43 33 30 1.552 0.889 43 29 30 9.30 0.894 41.0 42 23 22 6 9.91 0.871 46.3 41 37 40 5 1.456 43 23 20 1.554 0.888 43 23 20 9.11 0.868 40.1 42 17 16 5 9.81 0.859 45.8 42 35 38 5 1.451 43 23 24 1.563 0.883 43 33 30 9.21 0.867 38.8 42 37 36 5 9.81 0.854 45.1 42 37 36 5 1.451 43 33 34 1.569 0.879 44 39 36 9.08 0.865 40.1 42 19 22 5 11.57 0.851 19.2 44 39 40 5 1.437 43 21 22 1.592 0.867 43 21 22 9.09 0.862 39.6 42 21 20 5 9.92 0.848 43.0 42 19 22 5 1.429 43 35 36 1.595 0.865 43 19 20 9.08 0.857 39.1 42 17 20 4 9.61 0.845 46.3 42 21 20 6 1.389 43 35 28 1.599 0.863 44 35 14 9.05 0.854 39.1 42 19 18 4 9.45 0.845 48.1 42 11 38 5
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.19 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 7,100.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-23 Cycle: 23 Core Average Exposure: MWd/MTU 24058.3 Exposure: MWd/MTU (GWd) 7400.0 ( 751.43 )
| |
| Delta E: MWd/MTU, (GWd) 300.0 ( 30.46 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.173 4.596 37 0.720 0.746 3 24 Inlet Subcooling: Btu/lbm -23.79 24 0.391 12.205 38 0.413 0.642 47 16 Flow: Mlb/hr 69.88 ( 90.75 %) 23 0.610 16.378 39 0.435 0.791 17 48 22 0.703 19.356 40 0.504 0.934 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.734 21.255 41 0.868 1.219 39 38 51 -- -- -- -- -- 51 20 0.764 22.626 42 1.129 1.313 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 0.784 23.390 43 1.330 1.483 25 26 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.809 24.283 44 1.178 1.377 39 36 39 -- -- 42 -- 6 -- 6 -- 42 -- -- 39 17 0.833 24.987 45 1.198 1.331 41 18 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 0.860 25.475 31 -- -- -- 0 -- 20 -- 40 -- 6 -- -- -- 31 15 0.904 25.884 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 0.927 26.166 23 -- -- -- 6 -- 40 -- 20 -- 6 -- -- -- 23 13 1.012 26.318 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.069 27.381 15 -- -- 42 -- 6 -- 6 -- 42 -- -- 15 11 1.125 28.176 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.210 28.123 7 -- -- -- -- -- -- -- -- -- 7 9 1.287 28.824 3 -- -- -- -- -- 3 8 1.367 29.394 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.459 29.957 6 1.561 30.795 5 1.637 31.093*
| |
| 4 1.650* 30.425 Control Rod Density: % 6.66 3 1.558 28.577 2 1.229 22.356 k-effective: 0.99950 Bottom 1 0.344 6.479 Void Fraction: 0.519 Core Delta-P: psia 20.679 % AXIAL TILT -29.192 -13.388 Core Plate Delta-P: psia 16.124 AVG BOT 8ft/12ft 1.1600 1.0758 Coolant Temp: Deg-F 548.5 In Channel Flow: Mlb/hr 60.82 Active Channel Flow: Mlb/hr 58.56 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.2 (of total core flow)
| |
| Source Convergence 0.00049 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.483 43 25 26 1.489 0.927 43 27 28 9.18 0.910 44.1 41 13 16 5 10.16 0.882 44.7 42 21 24 6 1.481 43 31 28 1.524 0.906 43 25 22 9.19 0.910 43.8 41 37 40 5 10.16 0.879 44.5 42 23 22 6 1.480 43 25 22 1.527 0.904 43 31 28 9.25 0.896 41.7 42 21 24 6 9.87 0.874 47.0 41 13 16 5 1.465 43 33 30 1.547 0.892 43 29 30 9.24 0.893 41.5 42 23 22 6 9.86 0.872 46.9 41 37 40 5 1.460 43 23 20 1.548 0.891 43 23 20 9.07 0.870 40.7 42 17 16 5 9.77 0.860 46.4 42 35 38 5 1.455 43 33 34 1.556 0.887 43 33 30 9.18 0.869 39.4 42 37 36 5 9.77 0.855 45.7 42 37 36 5 1.455 43 23 24 1.573 0.877 44 39 36 9.03 0.866 40.7 42 19 22 5 9.86 0.847 43.6 42 19 22 5 1.441 43 21 22 1.587 0.870 43 21 22 9.04 0.862 40.2 42 21 20 5 11.52 0.847 20.1 44 39 40 5 1.434 43 35 36 1.588 0.869 43 19 20 9.05 0.859 39.7 42 17 20 4 9.40 0.845 48.7 42 11 38 5 1.394 43 35 28 1.598 0.864 44 35 14 9.02 0.856 39.6 42 19 18 4 9.54 0.844 46.9 42 21 20 6
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.20 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 7,400.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-24 Cycle: 23 Core Average Exposure: MWd/MTU 24059.3 Exposure: MWd/MTU (GWd) 7401.0 ( 751.53 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.147 4.596 37 0.742 0.776 3 24 Inlet Subcooling: Btu/lbm -24.86 24 0.332 12.206 38 0.424 0.658 47 16 Flow: Mlb/hr 67.18 ( 87.25 %) 23 0.522 16.379 39 0.446 0.809 17 48 22 0.609 19.356 40 0.517 0.975 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.651 21.256 41 0.892 1.273 39 38 51 -- -- -- -- -- 51 20 0.687 22.627 42 1.099 1.297 15 18 47 -- -- -- -- -- -- -- -- -- 47 19 0.715 23.391 43 1.215 1.448 37 16 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.751 24.284 44 1.215 1.445 39 18 39 -- -- -- 40 -- 6 -- 40 -- -- -- 39 17 0.787 24.988 45 1.269 1.418 41 20 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 0.830 25.476 31 -- -- 40 -- 0 -- 8 -- 0 -- 40 -- -- 31 15 0.894 25.885 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 0.941 26.167 23 -- -- 40 -- 0 -- 8 -- 0 -- 40 -- -- 23 13 1.047 26.319 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.121 27.382 15 -- -- -- 40 -- 6 -- 40 -- -- -- 15 11 1.189 28.177 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.286 28.124 7 -- -- -- -- -- -- -- -- -- 7 9 1.369 28.825 3 -- -- -- -- -- 3 8 1.451 29.396 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.540 29.959 6 1.631 30.796 5 1.684* 31.094*
| |
| 4 1.660 30.426 Control Rod Density: % 6.39 3 1.568 28.579 2 1.241 22.357 k-effective: 0.99966 Bottom 1 0.348 6.479 Void Fraction: 0.532 Core Delta-P: psia 19.719 % AXIAL TILT -34.325 -13.389 Core Plate Delta-P: psia 15.166 AVG BOT 8ft/12ft 1.1950 1.0758 Coolant Temp: Deg-F 548.4 In Channel Flow: Mlb/hr 58.36 Active Channel Flow: Mlb/hr 56.14 Total Bypass Flow (%): 13.1 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00034 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.448 43 37 16 1.448 0.953 44 39 18 9.45 0.916 41.8 42 33 14 6 10.38 0.901 44.7 42 19 14 6 1.445 44 39 18 1.474 0.937 45 39 22 9.62 0.915 40.0 42 35 16 6 10.50 0.899 43.1 42 35 16 6 1.426 43 35 18 1.504 0.917 45 31 14 9.07 0.898 43.9 42 11 32 6 10.21 0.886 44.8 42 11 22 6 1.418 45 41 20 1.506 0.916 45 43 26 9.11 0.897 43.4 41 43 24 6 11.89 0.874 18.2 44 13 36 4 1.417 45 39 22 1.512 0.913 45 41 20 9.25 0.893 41.4 41 13 38 4 9.91 0.872 46.3 41 43 24 6 1.405 43 37 20 1.515 0.911 45 39 26 9.00 0.888 43.6 41 37 14 5 10.18 0.868 42.8 42 13 20 4 1.398 45 31 14 1.522 0.907 45 41 18 9.26 0.886 40.5 42 37 18 5 10.31 0.868 41.1 42 15 36 5 1.397 45 41 18 1.544 0.894 44 35 14 9.23 0.884 40.6 42 13 34 5 11.79 0.867 19.1 44 35 14 6 1.396 45 33 12 1.546 0.892 45 33 12 8.94 0.870 42.2 42 11 28 6 9.68 0.866 48.1 42 11 38 4 1.392 45 39 26 1.550 0.890 45 35 12 8.87 0.868 42.7 42 11 38 4 9.64 0.861 48.0 41 13 38 4
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.21 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 7,401.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-25 Cycle: 23 Core Average Exposure: MWd/MTU 24558.3 Exposure: MWd/MTU (GWd) 7900.0 ( 802.20 )
| |
| Delta E: MWd/MTU, (GWd) 499.0 ( 50.67 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.149 4.675 37 0.738 0.771 3 24 Inlet Subcooling: Btu/lbm -24.79 24 0.336 12.385 38 0.420 0.654 47 16 Flow: Mlb/hr 67.38 ( 87.50 %) 23 0.528 16.663 39 0.442 0.804 17 48 22 0.617 19.688 40 0.513 0.969 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.658 21.611 41 0.887 1.270 39 38 51 -- -- -- -- -- 51 20 0.693 23.002 42 1.097 1.294 15 18 47 -- -- -- -- -- -- -- -- -- 47 19 0.721 23.781 43 1.221 1.454 37 16 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.755 24.693 44 1.219 1.450 39 18 39 -- -- -- 40 -- 6 -- 40 -- -- -- 39 17 0.791 25.416 45 1.273 1.424 41 20 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 0.833 25.924 31 -- -- 40 -- 0 -- 8 -- 0 -- 40 -- -- 31 15 0.895 26.354 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 0.941 26.661 23 -- -- 40 -- 0 -- 8 -- 0 -- 40 -- -- 23 13 1.046 26.823 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.119 27.921 15 -- -- -- 40 -- 6 -- 40 -- -- -- 15 11 1.186 28.749 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.280 28.717 7 -- -- -- -- -- -- -- -- -- 7 9 1.362 29.453 3 -- -- -- -- -- 3 8 1.442 30.061 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.531 30.665 6 1.624 31.545 5 1.679* 31.868*
| |
| 4 1.658 31.190 Control Rod Density: % 6.39 3 1.568 29.300 2 1.240 22.928 k-effective: 0.99963 Bottom 1 0.348 6.651 Void Fraction: 0.530 Core Delta-P: psia 19.783 % AXIAL TILT -33.902 -13.676 Core Plate Delta-P: psia 15.230 AVG BOT 8ft/12ft 1.1922 1.0772 Coolant Temp: Deg-F 548.4 In Channel Flow: Mlb/hr 58.54 Active Channel Flow: Mlb/hr 56.31 Total Bypass Flow (%): 13.1 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00037 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.454 43 37 16 1.457 0.947 44 39 18 9.37 0.917 42.8 42 33 14 6 10.29 0.902 45.8 42 19 14 6 1.450 44 39 18 1.486 0.929 45 39 22 9.54 0.917 41.0 42 35 16 6 10.41 0.899 44.2 42 35 16 6 1.433 43 35 18 1.514 0.912 45 31 14 8.99 0.899 44.9 42 11 32 6 10.10 0.885 45.8 42 11 22 6 1.424 45 41 20 1.516 0.910 45 43 26 9.04 0.899 44.3 41 43 24 6 9.82 0.872 47.4 41 43 24 6 1.419 45 39 22 1.522 0.907 45 41 20 9.19 0.896 42.3 41 13 38 4 10.11 0.871 43.8 42 13 20 4 1.411 43 37 20 1.529 0.903 45 39 26 8.95 0.892 44.5 41 37 14 5 10.23 0.869 42.2 42 15 36 5 1.403 45 41 18 1.529 0.902 45 41 18 9.20 0.889 41.5 42 37 18 5 9.61 0.867 49.2 42 11 38 4 1.403 45 33 12 1.553 0.889 44 35 14 9.17 0.887 41.6 42 13 34 5 11.78 0.866 17.3 44 13 36 4 1.401 45 31 14 1.554 0.888 45 33 12 8.84 0.873 43.6 42 11 38 4 9.57 0.862 49.0 41 13 38 4 1.394 45 39 26 1.556 0.887 45 35 12 8.85 0.870 43.1 42 11 28 6 9.50 0.859 49.4 41 37 14 5
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.22 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 7,900.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-26 Cycle: 23 Core Average Exposure: MWd/MTU 25058.3 Exposure: MWd/MTU (GWd) 8400.0 ( 852.98 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.151 4.756 37 0.734 0.765 3 24 Inlet Subcooling: Btu/lbm -24.79 24 0.340 12.567 38 0.416 0.651 47 16 Flow: Mlb/hr 67.38 ( 87.50 %) 23 0.534 16.951 39 0.439 0.800 17 48 22 0.623 20.025 40 0.509 0.964 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.664 21.971 41 0.883 1.267 39 38 51 -- -- -- -- -- 51 20 0.699 23.380 42 1.095 1.290 15 18 47 -- -- -- -- -- -- -- -- -- 47 19 0.726 24.175 43 1.226 1.459 37 16 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.760 25.106 44 1.224 1.456 39 18 39 -- -- -- 40 -- 6 -- 40 -- -- -- 39 17 0.795 25.848 45 1.278 1.430 41 20 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 0.836 26.374 31 -- -- 40 -- 0 -- 8 -- 0 -- 40 -- -- 31 15 0.897 26.825 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 0.942 27.156 23 -- -- 40 -- 0 -- 8 -- 0 -- 40 -- -- 23 13 1.046 27.328 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.118 28.461 15 -- -- -- 40 -- 6 -- 40 -- -- -- 15 11 1.184 29.321 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.275 29.308 7 -- -- -- -- -- -- -- -- -- 7 9 1.355 30.080 3 -- -- -- -- -- 3 8 1.434 30.724 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.523 31.369 6 1.616 32.292 5 1.673* 32.641*
| |
| 4 1.655 31.954 Control Rod Density: % 6.39 3 1.567 30.023 2 1.239 23.498 k-effective: 0.99965 Bottom 1 0.347 6.823 Void Fraction: 0.529 Core Delta-P: psia 19.768 % AXIAL TILT -33.476 -13.944 Core Plate Delta-P: psia 15.215 AVG BOT 8ft/12ft 1.1896 1.0786 Coolant Temp: Deg-F 548.4 In Channel Flow: Mlb/hr 58.54 Active Channel Flow: Mlb/hr 56.32 Total Bypass Flow (%): 13.1 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00031 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.459 43 37 16 1.463 0.943 44 39 18 9.29 0.919 43.8 42 33 14 6 10.20 0.902 46.9 42 19 14 6 1.456 44 39 18 1.497 0.922 45 39 22 9.45 0.917 42.0 42 35 16 6 10.30 0.898 45.3 42 35 16 6 1.439 43 35 18 1.522 0.907 45 31 14 8.98 0.902 45.3 41 43 24 6 10.01 0.885 46.9 42 11 22 6 1.430 45 41 20 1.523 0.906 45 43 26 8.93 0.901 45.8 42 11 32 6 9.75 0.873 48.4 41 43 24 6 1.422 45 39 22 1.528 0.903 45 41 20 9.13 0.899 43.3 41 13 38 4 10.03 0.872 44.9 42 13 20 4 1.416 43 37 20 1.533 0.900 45 41 18 8.89 0.895 45.5 41 37 14 5 10.14 0.869 43.3 42 15 36 5 1.409 45 41 18 1.540 0.896 45 39 26 9.12 0.890 42.4 42 37 18 5 9.54 0.869 50.2 42 11 38 4 1.409 45 33 12 1.558 0.886 44 35 14 9.11 0.889 42.5 42 13 34 5 9.50 0.864 50.0 41 13 38 4 1.405 45 31 14 1.558 0.886 45 33 12 8.82 0.879 44.5 42 11 38 4 9.43 0.861 50.4 41 37 14 5 1.396 45 39 26 1.559 0.885 45 35 12 8.71 0.871 44.9 42 11 28 5 11.69 0.859 19.8 44 13 36 4
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.23 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 8,400.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-27 Cycle: 23 Core Average Exposure: MWd/MTU 25508.3 Exposure: MWd/MTU (GWd) 8850.0 ( 898.67 )
| |
| Delta E: MWd/MTU, (GWd) 450.0 ( 45.70 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.152 4.829 37 0.731 0.761 3 24 Inlet Subcooling: Btu/lbm -24.79 24 0.343 12.733 38 0.413 0.648 47 16 Flow: Mlb/hr 67.38 ( 87.50 %) 23 0.540 17.214 39 0.436 0.797 17 48 22 0.629 20.331 40 0.505 0.959 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.670 22.298 41 0.880 1.265 39 16 51 -- -- -- -- -- 51 20 0.704 23.724 42 1.093 1.286 15 18 47 -- -- -- -- -- -- -- -- -- 47 19 0.731 24.532 43 1.228 1.464 37 16 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.766 25.480 44 1.228 1.461 39 18 39 -- -- -- 40 -- 6 -- 40 -- -- -- 39 17 0.800 26.239 45 1.283 1.435 41 20 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 0.840 26.781 31 -- -- 40 -- 0 -- 8 -- 0 -- 40 -- -- 31 15 0.901 27.251 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 0.946 27.603 23 -- -- 40 -- 0 -- 8 -- 0 -- 40 -- -- 23 13 1.049 27.783 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.120 28.947 15 -- -- -- 40 -- 6 -- 40 -- -- -- 15 11 1.185 29.835 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.273 29.838 7 -- -- -- -- -- -- -- -- -- 7 9 1.351 30.641 3 -- -- -- -- -- 3 8 1.428 31.318 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.515 32.000 6 1.607 32.960 5 1.663* 33.333*
| |
| 4 1.646 32.638 Control Rod Density: % 6.39 3 1.561 30.671 2 1.234 24.011 k-effective: 0.99967 Bottom 1 0.346 6.978 Void Fraction: 0.527 Core Delta-P: psia 19.750 % AXIAL TILT -33.023 -14.169 Core Plate Delta-P: psia 15.197 AVG BOT 8ft/12ft 1.1872 1.0797 Coolant Temp: Deg-F 548.4 In Channel Flow: Mlb/hr 58.55 Active Channel Flow: Mlb/hr 56.34 Total Bypass Flow (%): 13.1 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00022 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.464 43 37 16 1.467 0.940 44 39 18 9.20 0.918 44.6 42 33 14 6 10.10 0.900 47.9 42 19 14 6 1.461 44 39 18 1.505 0.917 45 39 22 9.35 0.916 42.9 42 35 16 6 10.19 0.896 46.2 42 35 16 6 1.443 43 35 18 1.528 0.903 45 43 26 8.92 0.904 46.1 41 43 24 6 9.93 0.885 47.8 42 11 22 6 1.435 45 41 20 1.529 0.903 45 31 14 8.86 0.903 46.6 42 11 32 6 9.68 0.874 49.3 41 43 24 6 1.425 45 39 22 1.533 0.900 45 41 20 9.05 0.898 44.2 41 13 38 4 9.86 0.870 46.7 42 13 20 5 1.421 43 37 20 1.536 0.899 45 41 18 8.81 0.895 46.3 41 37 14 5 9.46 0.868 51.1 42 11 38 4 1.416 45 41 18 1.549 0.891 45 39 26 9.03 0.890 43.4 42 13 34 5 9.84 0.867 46.5 42 37 18 5 1.415 45 33 12 1.558 0.886 44 35 14 9.03 0.889 43.3 42 37 18 5 9.42 0.863 50.9 41 13 38 4 1.409 45 31 14 1.561 0.884 45 35 12 8.78 0.882 45.4 42 11 38 4 9.35 0.860 51.3 41 37 14 5 1.400 43 33 16 1.562 0.884 45 33 12 8.65 0.873 45.7 42 11 28 5 11.60 0.853 21.1 44 13 36 4
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.24 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 8,850.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-28 Cycle: 23 Core Average Exposure: MWd/MTU 26008.2 Exposure: MWd/MTU (GWd) 9350.0 ( 949.44 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.155 4.911 37 0.728 0.757 3 24 Inlet Subcooling: Btu/lbm -24.79 24 0.349 12.919 38 0.410 0.645 47 16 Flow: Mlb/hr 67.38 ( 87.50 %) 23 0.551 17.510 39 0.434 0.793 17 48 22 0.642 20.676 40 0.502 0.955 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.682 22.666 41 0.877 1.262 39 16 51 -- -- -- -- -- 51 20 0.716 24.111 42 1.090 1.282 15 18 47 -- -- -- -- -- -- -- -- -- 47 19 0.743 24.933 43 1.230 1.466 37 16 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.776 25.899 44 1.233 1.466 39 18 39 -- -- -- 40 -- 6 -- 40 -- -- -- 39 17 0.810 26.677 45 1.288 1.441 41 20 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 0.849 27.237 31 -- -- 40 -- 0 -- 8 -- 0 -- 40 -- -- 31 15 0.908 27.726 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 0.952 28.102 23 -- -- 40 -- 0 -- 8 -- 0 -- 40 -- -- 23 13 1.054 28.290 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.124 29.488 15 -- -- -- 40 -- 6 -- 40 -- -- -- 15 11 1.186 30.407 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.271 30.427 7 -- -- -- -- -- -- -- -- -- 7 9 1.345 31.262 3 -- -- -- -- -- 3 8 1.419 31.974 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.503 32.695 6 1.591 33.698 5 1.644* 34.095*
| |
| 4 1.626 33.393 Control Rod Density: % 6.39 3 1.543 31.387 2 1.220 24.576 k-effective: 0.99971 Bottom 1 0.342 7.149 Void Fraction: 0.525 Core Delta-P: psia 19.716 % AXIAL TILT -32.083 -14.395 Core Plate Delta-P: psia 15.163 AVG BOT 8ft/12ft 1.1819 1.0808 Coolant Temp: Deg-F 548.4 In Channel Flow: Mlb/hr 58.57 Active Channel Flow: Mlb/hr 56.36 Total Bypass Flow (%): 13.1 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00049 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.466 43 37 16 1.471 0.938 44 39 18 9.05 0.912 45.6 42 33 14 6 9.93 0.894 48.9 42 19 14 6 1.466 44 39 18 1.515 0.911 45 39 22 9.18 0.909 43.8 42 35 16 6 10.01 0.888 47.3 42 35 16 6 1.446 43 35 18 1.532 0.901 45 31 14 8.84 0.905 47.0 41 43 24 6 9.80 0.882 48.9 42 11 22 6 1.441 45 41 20 1.533 0.900 45 43 26 8.77 0.902 47.6 42 11 32 6 9.57 0.873 50.3 41 43 24 6 1.429 45 39 22 1.538 0.897 45 41 20 8.89 0.891 45.1 41 13 38 4 9.72 0.865 47.7 42 13 20 5 1.425 43 37 20 1.540 0.896 45 41 18 8.67 0.889 47.2 41 37 14 5 9.30 0.862 52.1 42 11 38 4 1.421 45 41 18 1.558 0.886 44 35 14 8.90 0.886 44.4 42 13 34 5 9.66 0.859 47.5 42 37 18 5 1.420 45 33 12 1.558 0.886 45 39 26 8.86 0.881 44.3 42 37 18 5 9.26 0.857 51.9 41 13 38 4 1.412 45 31 14 1.564 0.882 44 39 14 8.67 0.880 46.3 42 11 38 4 9.21 0.855 52.3 41 37 14 5 1.405 43 33 16 1.565 0.882 45 35 12 9.22 0.872 39.2 42 29 10 4 9.89 0.850 43.6 42 29 10 4
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.25 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 9,350.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-29 Cycle: 23 Core Average Exposure: MWd/MTU 26009.3 Exposure: MWd/MTU (GWd) 9351.0 ( 949.55 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.178 4.912 37 0.687 0.695 3 24 Inlet Subcooling: Btu/lbm -25.10 24 0.399 12.919 38 0.390 0.622 47 16 Flow: Mlb/hr 66.61 ( 86.50 %) 23 0.624 17.510 39 0.418 0.764 17 48 22 0.718 20.677 40 0.478 0.908 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.742 22.667 41 0.831 1.218 37 14 51 -- -- -- -- -- 51 20 0.758 24.111 42 1.136 1.320 35 24 47 -- -- -- -- -- -- -- -- -- 47 19 0.769 24.934 43 1.374 1.504 33 24 43 -- -- -- -- -- 8 -- -- -- -- -- 43 18 0.789 25.900 44 1.160 1.407 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.810 26.678 45 1.226 1.432 39 22 35 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 35 16 0.838 27.238 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.886 27.727 27 -- -- 8 -- 40 -- 6 -- 40 -- 8 -- -- 27 14 0.921 28.103 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.013 28.291 19 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 19 12 1.074 29.489 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.130 30.408 11 -- -- -- -- -- 8 -- -- -- -- -- 11 10 1.208 30.428 7 -- -- -- -- -- -- -- -- -- 7 9 1.278 31.264 3 -- -- -- -- -- 3 8 1.351 31.975 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.438 32.697 6 1.538 33.699 5 1.616 34.097*
| |
| 4 1.648* 33.394 Control Rod Density: % 6.11 3 1.606 31.388 2 1.298 24.577 k-effective: 0.99985 Bottom 1 0.369 7.149 Void Fraction: 0.522 Core Delta-P: psia 19.354 % AXIAL TILT -29.694 -14.395 Core Plate Delta-P: psia 14.806 AVG BOT 8ft/12ft 1.1610 1.0808 Coolant Temp: Deg-F 548.4 In Channel Flow: Mlb/hr 57.92 Active Channel Flow: Mlb/hr 55.74 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00044 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.504 43 33 24 1.492 0.925 43 29 20 9.14 0.909 44.3 42 19 28 6 10.00 0.888 47.4 42 19 28 6 1.496 43 29 20 1.494 0.924 43 33 24 9.13 0.908 44.3 42 27 20 6 9.96 0.885 47.5 42 27 20 6 1.494 43 27 22 1.498 0.921 43 27 22 8.78 0.893 46.4 41 37 14 4 9.81 0.867 46.9 42 13 34 4 1.485 43 31 26 1.507 0.916 45 39 22 9.04 0.891 43.5 42 13 34 4 9.69 0.866 48.0 42 19 14 4 1.479 43 31 22 1.520 0.908 45 31 14 8.88 0.890 45.1 41 13 38 4 11.57 0.860 22.4 44 35 14 3 1.467 43 37 24 1.530 0.902 43 31 26 8.93 0.889 44.5 42 33 14 4 9.28 0.860 52.1 42 11 38 4 1.467 43 29 24 1.550 0.890 43 37 24 8.65 0.878 46.3 42 11 38 4 9.32 0.859 51.6 41 37 14 4 1.462 43 29 16 1.553 0.888 43 31 22 8.67 0.876 45.8 42 37 12 4 11.59 0.858 21.8 44 13 36 3 1.453 43 35 26 1.555 0.887 43 29 16 8.60 0.869 45.8 42 9 34 4 9.20 0.855 52.4 42 37 12 4 1.447 43 27 18 1.568 0.880 44 39 18 8.83 0.865 42.8 42 17 30 5 9.24 0.855 51.9 41 13 38 4
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.26 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 9,351.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-30 Cycle: 23 Core Average Exposure: MWd/MTU 26358.2 Exposure: MWd/MTU (GWd) 9700.0 ( 984.98 )
| |
| Delta E: MWd/MTU, (GWd) 349.0 ( 35.44 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.181 4.979 37 0.687 0.694 3 24 Inlet Subcooling: Btu/lbm -25.11 24 0.406 13.070 38 0.389 0.621 47 16 Flow: Mlb/hr 66.61 ( 86.50 %) 23 0.636 17.749 39 0.417 0.763 17 48 22 0.731 20.951 40 0.476 0.906 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.756 22.951 41 0.831 1.217 37 14 51 -- -- -- -- -- 51 20 0.772 24.402 42 1.134 1.316 35 24 47 -- -- -- -- -- -- -- -- -- 47 19 0.782 25.228 43 1.373 1.501 33 24 43 -- -- -- -- -- 8 -- -- -- -- -- 43 18 0.802 26.203 44 1.164 1.410 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.823 26.988 45 1.230 1.434 39 22 35 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 35 16 0.849 27.555 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.897 28.055 27 -- -- 8 -- 40 -- 6 -- 40 -- 8 -- -- 27 14 0.930 28.443 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.022 28.634 19 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 19 12 1.082 29.853 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.135 30.789 11 -- -- -- -- -- 8 -- -- -- -- -- 11 10 1.210 30.819 7 -- -- -- -- -- -- -- -- -- 7 9 1.276 31.674 3 -- -- -- -- -- 3 8 1.344 32.409 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.426 33.157 6 1.520 34.191 5 1.593 34.613*
| |
| 4 1.619* 33.920 Control Rod Density: % 6.11 3 1.575 31.900 2 1.272 24.990 k-effective: 0.99986 Bottom 1 0.361 7.275 Void Fraction: 0.519 Core Delta-P: psia 19.313 % AXIAL TILT -28.560 -14.502 Core Plate Delta-P: psia 14.765 AVG BOT 8ft/12ft 1.1551 1.0812 Coolant Temp: Deg-F 548.4 In Channel Flow: Mlb/hr 57.94 Active Channel Flow: Mlb/hr 55.76 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.3 (of total core flow)
| |
| Source Convergence 0.00049 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.501 43 33 24 1.491 0.926 43 29 20 8.90 0.892 45.0 42 19 28 6 9.74 0.871 48.2 42 19 28 6 1.495 43 29 20 1.494 0.923 43 33 24 8.90 0.891 45.0 42 27 20 6 9.71 0.868 48.2 42 27 20 6 1.490 43 27 22 1.500 0.920 43 27 22 8.61 0.881 47.1 41 37 14 4 9.61 0.855 47.6 42 13 34 4 1.482 43 31 26 1.502 0.919 45 39 22 8.86 0.879 44.2 42 13 34 4 9.47 0.851 48.7 42 19 14 4 1.477 43 31 22 1.517 0.910 45 31 14 8.71 0.879 45.8 41 13 38 4 9.11 0.849 52.8 42 11 38 4 1.469 43 37 24 1.531 0.901 43 31 26 8.72 0.874 45.1 42 33 14 4 9.14 0.848 52.3 41 37 14 4 1.463 43 29 24 1.546 0.893 43 37 24 8.52 0.870 46.9 42 11 38 4 11.35 0.846 22.8 44 13 36 3 1.462 43 29 16 1.552 0.889 43 29 16 8.53 0.867 46.4 42 37 12 4 11.27 0.845 23.4 44 35 14 3 1.455 43 35 26 1.552 0.889 43 31 22 8.47 0.862 46.5 42 9 34 4 9.07 0.844 52.6 41 13 38 4 1.449 43 27 18 1.562 0.884 44 39 18 8.40 0.855 46.5 42 33 10 4 9.02 0.844 53.1 42 37 12 4
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.27 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 9,700.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-31 Cycle: 23 Core Average Exposure: MWd/MTU 26858.3 Exposure: MWd/MTU (GWd) 10200.0 (1035.76 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.186 5.077 37 0.686 0.692 3 24 Inlet Subcooling: Btu/lbm -24.94 24 0.416 13.291 38 0.387 0.619 47 16 Flow: Mlb/hr 66.99 ( 87.00 %) 23 0.654 18.099 39 0.415 0.761 17 48 22 0.752 21.354 40 0.474 0.903 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.776 23.368 41 0.829 1.216 37 14 51 -- -- -- -- -- 51 20 0.792 24.828 42 1.132 1.311 35 24 47 -- -- -- -- -- -- -- -- -- 47 19 0.803 25.660 43 1.373 1.499 33 24 43 -- -- -- -- -- 8 -- -- -- -- -- 43 18 0.823 26.645 44 1.169 1.415 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.843 27.441 45 1.234 1.437 39 22 35 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 35 16 0.869 28.019 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.916 28.531 27 -- -- 8 -- 40 -- 6 -- 40 -- 8 -- -- 27 14 0.948 28.937 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.039 29.131 19 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 19 12 1.097 30.378 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.147 31.339 11 -- -- -- -- -- 8 -- -- -- -- -- 11 10 1.215 31.380 7 -- -- -- -- -- -- -- -- -- 7 9 1.275 32.262 3 -- -- -- -- -- 3 8 1.336 33.027 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.410 33.811 6 1.492 34.885 5 1.554 35.338*
| |
| 4 1.568* 34.655 Control Rod Density: % 6.11 3 1.517 32.612 2 1.224 25.565 k-effective: 1.00000 Bottom 1 0.347 7.451 Void Fraction: 0.514 Core Delta-P: psia 19.400 % AXIAL TILT -26.731 -14.621 Core Plate Delta-P: psia 14.851 AVG BOT 8ft/12ft 1.1458 1.0817 Coolant Temp: Deg-F 548.3 In Channel Flow: Mlb/hr 58.31 Active Channel Flow: Mlb/hr 56.14 Total Bypass Flow (%): 13.0 (of total core flow)
| |
| Total Water Rod Flow (%): 3.2 (of total core flow)
| |
| Source Convergence 0.00046 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.499 43 33 24 1.492 0.925 43 29 20 8.58 0.868 45.9 42 19 28 6 9.38 0.846 49.1 42 19 28 6 1.494 43 29 20 1.499 0.921 43 33 24 8.58 0.867 45.9 42 27 20 6 9.36 0.845 49.2 42 27 20 6 1.486 43 27 22 1.501 0.919 45 39 22 8.30 0.858 48.0 41 37 14 4 9.28 0.833 48.6 42 13 34 4 1.479 43 31 26 1.505 0.917 43 27 22 8.42 0.858 46.7 41 13 38 4 8.81 0.829 53.7 42 11 38 4 1.476 43 31 22 1.517 0.910 45 31 14 8.55 0.857 45.1 42 13 34 4 8.82 0.826 53.2 41 37 14 4 1.470 43 37 24 1.535 0.899 43 31 26 8.27 0.853 47.8 42 11 38 4 9.10 0.825 49.7 42 19 14 4 1.462 43 29 16 1.545 0.893 43 37 24 8.38 0.848 46.0 42 33 14 4 8.95 0.824 51.4 42 43 20 4 1.460 43 29 24 1.553 0.889 43 29 16 8.26 0.848 47.3 42 37 12 4 8.77 0.824 53.5 41 13 38 4 1.457 43 35 26 1.555 0.887 43 31 22 8.24 0.846 47.4 42 9 34 4 8.71 0.823 54.1 42 37 12 4 1.451 43 27 18 1.559 0.885 44 39 18 8.15 0.837 47.4 42 33 10 4 10.84 0.822 24.9 44 13 36 4
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.28 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 10,200.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-32 Cycle: 23 Core Average Exposure: MWd/MTU 27358.2 Exposure: MWd/MTU (GWd) 10700.0 (1086.53 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.192 5.178 37 0.684 0.690 3 24 Inlet Subcooling: Btu/lbm -24.79 24 0.428 13.518 38 0.385 0.618 47 16 Flow: Mlb/hr 67.38 ( 87.50 %) 23 0.675 18.460 39 0.413 0.760 17 48 22 0.778 21.769 40 0.472 0.901 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.802 23.798 41 0.828 1.215 37 14 51 -- -- -- -- -- 51 20 0.818 25.266 42 1.130 1.307 35 24 47 -- -- -- -- -- -- -- -- -- 47 19 0.829 26.104 43 1.373 1.498 33 24 43 -- -- -- -- -- 8 -- -- -- -- -- 43 18 0.849 27.100 44 1.173 1.418 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.869 27.908 45 1.237 1.439 39 22 35 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 35 16 0.894 28.494 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.940 29.019 27 -- -- 8 -- 40 -- 6 -- 40 -- 8 -- -- 27 14 0.971 29.442 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.061 29.638 19 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 19 12 1.117 30.912 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.161 31.896 11 -- -- -- -- -- 8 -- -- -- -- -- 11 10 1.224 31.944 7 -- -- -- -- -- -- -- -- -- 7 9 1.276 32.850 3 -- -- -- -- -- 3 8 1.327 33.641 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.389 34.456 6 1.457 35.565 5 1.504* 36.043*
| |
| 4 1.503 35.363 Control Rod Density: % 6.11 3 1.444 33.295 2 1.163 26.115 k-effective: 1.00015 Bottom 1 0.329 7.619 Void Fraction: 0.507 Core Delta-P: psia 19.467 % AXIAL TILT -24.436 -14.697 Core Plate Delta-P: psia 14.919 AVG BOT 8ft/12ft 1.1343 1.0819 Coolant Temp: Deg-F 548.3 In Channel Flow: Mlb/hr 58.69 Active Channel Flow: Mlb/hr 56.52 Total Bypass Flow (%): 12.9 (of total core flow)
| |
| Total Water Rod Flow (%): 3.2 (of total core flow)
| |
| Source Convergence 0.00041 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.498 43 33 24 1.490 0.926 43 29 20 8.23 0.840 46.8 42 27 20 6 8.98 0.818 50.1 42 19 28 6 1.495 43 29 20 1.499 0.920 43 33 24 8.23 0.840 46.8 42 19 28 6 8.97 0.817 50.1 42 27 20 6 1.484 43 27 22 1.500 0.920 45 39 22 8.05 0.828 47.5 41 13 38 4 8.44 0.808 54.6 42 11 38 4 1.477 43 31 26 1.506 0.916 43 27 22 7.95 0.827 48.7 42 11 38 4 8.22 0.807 55.7 42 37 12 5 1.476 43 31 22 1.516 0.911 45 31 14 7.93 0.827 48.8 41 37 14 4 8.86 0.803 49.6 42 13 34 4 1.471 43 37 24 1.537 0.898 43 31 26 8.17 0.827 46.0 42 13 34 4 8.40 0.801 54.4 41 13 38 4 1.463 43 29 16 1.543 0.894 43 37 24 7.93 0.822 48.2 42 9 34 4 8.60 0.799 52.3 42 43 20 4 1.461 43 35 26 1.551 0.890 43 29 16 7.93 0.821 48.2 42 37 12 4 8.32 0.799 54.8 41 37 14 5 1.459 43 29 24 1.551 0.890 43 31 22 7.98 0.815 46.9 42 33 14 4 10.37 0.794 26.0 44 39 18 4 1.455 43 27 18 1.554 0.888 44 39 18 7.83 0.812 48.2 42 33 10 4 8.65 0.791 50.6 42 19 14 4
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.29 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 10,700.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-33 Cycle: 23 Core Average Exposure: MWd/MTU 27858.3 Exposure: MWd/MTU (GWd) 11200.0 (1137.30 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.198 5.283 37 0.684 0.689 3 24 Inlet Subcooling: Btu/lbm -24.71 24 0.442 13.753 38 0.384 0.617 47 16 Flow: Mlb/hr 67.57 ( 87.75 %) 23 0.700 18.833 39 0.412 0.758 17 48 22 0.807 22.199 40 0.470 0.898 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.832 24.242 41 0.827 1.213 37 14 51 -- -- -- -- -- 51 20 0.849 25.719 42 1.128 1.304 35 24 47 -- -- -- -- -- -- -- -- -- 47 19 0.860 26.563 43 1.373 1.497 33 24 43 -- -- -- -- -- 8 -- -- -- -- -- 43 18 0.881 27.571 44 1.176 1.420 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.901 28.389 45 1.240 1.441 39 22 35 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 35 16 0.924 28.985 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 0.969 29.522 27 -- -- 8 -- 40 -- 6 -- 40 -- 8 -- -- 27 14 0.997 29.959 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.087 30.156 19 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 19 12 1.139 31.457 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.178 32.460 11 -- -- -- -- -- 8 -- -- -- -- -- 11 10 1.233 32.513 7 -- -- -- -- -- -- -- -- -- 7 9 1.276 33.439 3 -- -- -- -- -- 3 8 1.317 34.250 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.364 35.091 6 1.416 36.228 5 1.446* 36.723*
| |
| 4 1.427 36.038 Control Rod Density: % 6.11 3 1.359 33.941 2 1.092 26.634 k-effective: 1.00025 Bottom 1 0.309 7.777 Void Fraction: 0.499 Core Delta-P: psia 19.446 % AXIAL TILT -21.730 -14.724 Core Plate Delta-P: psia 14.899 AVG BOT 8ft/12ft 1.1208 1.0819 Coolant Temp: Deg-F 548.2 In Channel Flow: Mlb/hr 58.90 Active Channel Flow: Mlb/hr 56.74 Total Bypass Flow (%): 12.8 (of total core flow)
| |
| Total Water Rod Flow (%): 3.2 (of total core flow)
| |
| Source Convergence 0.00040 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.497 43 33 24 1.486 0.929 43 29 20 7.86 0.810 47.6 42 27 20 6 8.02 0.794 56.0 42 11 38 5 1.495 43 29 20 1.495 0.923 45 39 22 7.85 0.809 47.6 42 19 28 6 7.89 0.792 56.5 42 37 12 5 1.482 43 27 22 1.497 0.922 43 33 24 7.57 0.795 49.5 42 11 38 4 8.57 0.787 51.0 42 19 28 6 1.476 43 31 22 1.504 0.918 43 27 22 7.50 0.794 50.2 41 39 16 5 8.56 0.786 51.0 42 27 20 6 1.476 43 31 26 1.511 0.913 45 31 14 7.71 0.793 47.6 42 13 34 5 7.97 0.786 55.8 41 13 38 5 1.473 43 37 24 1.535 0.899 43 31 26 7.47 0.793 50.3 41 37 14 5 7.79 0.784 56.6 41 15 40 5 1.464 43 35 26 1.536 0.898 43 37 24 7.56 0.791 49.0 42 9 34 4 7.99 0.772 55.0 42 13 34 5 1.464 43 29 16 1.544 0.894 44 39 18 7.53 0.787 49.0 42 37 12 4 7.64 0.771 56.7 42 11 32 5 1.458 43 27 18 1.544 0.894 43 29 16 7.45 0.779 49.0 42 33 10 4 7.74 0.770 56.2 42 33 14 5 1.457 43 29 24 1.544 0.894 43 31 22 7.43 0.778 49.1 42 33 14 5 8.20 0.769 53.4 42 43 20 5
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.30 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 11,200.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-34 Cycle: 23 Core Average Exposure: MWd/MTU 28358.3 Exposure: MWd/MTU (GWd) 11700.0 (1188.07 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.206 5.391 37 0.683 0.687 3 24 Inlet Subcooling: Btu/lbm -24.63 24 0.458 13.995 38 0.383 0.615 47 16 Flow: Mlb/hr 67.76 ( 88.00 %) 23 0.728 19.221 39 0.411 0.757 17 48 22 0.841 22.646 40 0.468 0.895 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.866 24.704 41 0.826 1.213 37 14 51 -- -- -- -- -- 51 20 0.883 26.191 42 1.127 1.301 35 24 47 -- -- -- -- -- -- -- -- -- 47 19 0.895 27.041 43 1.373 1.496 33 24 43 -- -- -- -- -- 8 -- -- -- -- -- 43 18 0.916 28.060 44 1.179 1.422 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.935 28.889 45 1.243 1.442 39 22 35 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 35 16 0.957 29.492 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.000 30.039 27 -- -- 8 -- 40 -- 6 -- 40 -- 8 -- -- 27 14 1.026 30.492 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.114 30.687 19 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 19 12 1.162 32.012 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.195 33.033 11 -- -- -- -- -- 8 -- -- -- -- -- 11 10 1.242 33.086 7 -- -- -- -- -- -- -- -- -- 7 9 1.276 34.027 3 -- -- -- -- -- 3 8 1.304 34.854 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.337 35.713 6 1.371 36.870 5 1.381* 37.375*
| |
| 4 1.343 36.677 Control Rod Density: % 6.11 3 1.264 34.545 2 1.013 27.119 k-effective: 1.00037 Bottom 1 0.286 7.924 Void Fraction: 0.491 Core Delta-P: psia 19.413 % AXIAL TILT -18.683 -14.697 Core Plate Delta-P: psia 14.866 AVG BOT 8ft/12ft 1.1054 1.0817 Coolant Temp: Deg-F 548.1 In Channel Flow: Mlb/hr 59.12 Active Channel Flow: Mlb/hr 56.98 Total Bypass Flow (%): 12.7 (of total core flow)
| |
| Total Water Rod Flow (%): 3.2 (of total core flow)
| |
| Source Convergence 0.00045 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.496 43 33 24 1.481 0.932 43 29 20 7.48 0.776 48.4 42 27 20 6 7.68 0.776 56.8 42 11 38 5 1.495 43 29 20 1.490 0.926 45 39 22 7.57 0.776 47.2 42 19 28 7 7.55 0.774 57.3 42 37 12 5 1.480 43 27 22 1.495 0.923 43 33 24 7.24 0.768 50.5 42 11 38 5 7.63 0.768 56.6 41 13 38 5 1.474 43 31 22 1.501 0.920 43 27 22 7.12 0.766 51.6 41 13 16 5 7.46 0.766 57.4 41 15 40 5 1.473 43 37 24 1.504 0.918 45 31 14 7.37 0.765 48.4 42 13 34 5 8.36 0.757 49.6 42 19 28 8 1.473 43 31 26 1.530 0.902 43 31 26 7.14 0.764 51.1 41 37 14 5 7.85 0.755 54.8 42 27 20 6 1.467 43 35 26 1.531 0.901 43 37 24 7.19 0.763 50.4 42 9 34 5 7.66 0.755 55.8 42 13 34 5 1.464 43 29 16 1.534 0.900 44 39 18 7.17 0.760 50.2 42 37 12 5 7.32 0.754 57.5 42 11 32 5 1.461 43 27 18 1.537 0.898 43 31 22 7.07 0.751 50.5 42 33 10 5 7.40 0.751 56.9 42 33 14 5 1.455 43 29 24 1.539 0.897 43 29 16 6.99 0.750 51.4 42 11 32 5 7.80 0.749 54.7 42 9 34 5
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.31 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 11,700.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-35 Cycle: 23 Core Average Exposure: MWd/MTU 28758.3 Exposure: MWd/MTU (GWd) 12100.0 (1228.69 )
| |
| Delta E: MWd/MTU, (GWd) 400.0 ( 40.62 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.211 5.480 37 0.683 0.687 3 24 Inlet Subcooling: Btu/lbm -24.47 24 0.471 14.195 38 0.381 0.614 47 16 Flow: Mlb/hr 68.14 ( 88.50 %) 23 0.751 19.542 39 0.410 0.755 17 48 22 0.867 23.017 40 0.467 0.894 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.893 25.087 41 0.826 1.212 37 14 51 -- -- -- -- -- 51 20 0.912 26.582 42 1.126 1.297 35 24 47 -- -- -- -- -- -- -- -- -- 47 19 0.923 27.437 43 1.372 1.494 33 24 43 -- -- -- -- -- 8 -- -- -- -- -- 43 18 0.945 28.465 44 1.182 1.424 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.964 29.303 45 1.245 1.443 39 22 35 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 35 16 0.984 29.911 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.026 30.466 27 -- -- 8 -- 40 -- 6 -- 40 -- 8 -- -- 27 14 1.050 30.928 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.136 31.121 19 -- -- -- -- 6 -- 40 -- 6 -- -- -- -- 19 12 1.181 32.464 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.209 33.496 11 -- -- -- -- -- 8 -- -- -- -- -- 11 10 1.249 33.547 7 -- -- -- -- -- -- -- -- -- 7 9 1.275 34.497 3 -- -- -- -- -- 3 8 1.294 35.333 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.314 36.202 6 1.335* 37.369 5 1.328 37.874*
| |
| 4 1.275 37.159 Control Rod Density: % 6.11 3 1.189 34.997 2 0.949 27.481 k-effective: 1.00048 Bottom 1 0.268 8.034 Void Fraction: 0.483 Core Delta-P: psia 19.478 % AXIAL TILT -16.221 -14.638 Core Plate Delta-P: psia 14.932 AVG BOT 8ft/12ft 1.0930 1.0813 Coolant Temp: Deg-F 548.1 In Channel Flow: Mlb/hr 59.51 Active Channel Flow: Mlb/hr 57.36 Total Bypass Flow (%): 12.7 (of total core flow)
| |
| Total Water Rod Flow (%): 3.1 (of total core flow)
| |
| Source Convergence 0.00032 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.494 43 33 24 1.482 0.931 43 29 20 7.48 0.764 46.9 42 19 28 8 7.40 0.761 57.4 42 11 38 5 1.493 43 29 20 1.488 0.927 45 39 22 7.46 0.763 47.0 42 27 20 8 7.27 0.758 58.0 42 37 12 5 1.477 43 27 22 1.495 0.923 43 33 24 6.99 0.747 51.1 42 11 38 5 7.35 0.753 57.3 41 13 38 5 1.473 43 37 24 1.501 0.919 45 31 14 6.86 0.742 52.2 41 13 16 5 7.18 0.750 58.0 41 15 40 5 1.472 43 31 22 1.503 0.918 43 27 22 6.95 0.742 51.0 42 9 34 5 8.17 0.744 50.3 42 19 28 8 1.470 43 31 26 1.529 0.903 43 37 24 7.09 0.741 49.0 42 13 34 5 8.13 0.742 50.4 42 27 20 8 1.468 43 35 26 1.529 0.902 44 39 18 6.87 0.740 51.7 41 37 14 5 7.38 0.739 56.4 42 13 34 5 1.464 43 29 16 1.531 0.902 43 31 26 6.92 0.738 50.8 42 37 12 5 7.06 0.738 58.1 42 11 32 5 1.462 43 27 18 1.535 0.899 43 31 22 7.31 0.732 45.0 42 17 30 8 7.53 0.735 55.4 42 9 34 5 1.451 43 29 24 1.535 0.899 43 35 26 7.21 0.729 46.0 42 29 18 8 7.11 0.733 57.5 42 33 14 5
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.32 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 12,100.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-36 Cycle: 23 Core Average Exposure: MWd/MTU 28759.3 Exposure: MWd/MTU (GWd) 12101.0 (1228.79 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.176 5.481 37 0.704 0.718 3 24 Inlet Subcooling: Btu/lbm -24.47 24 0.392 14.195 38 0.395 0.622 47 16 Flow: Mlb/hr 68.14 ( 88.50 %) 23 0.630 19.543 39 0.421 0.791 17 48 22 0.740 23.018 40 0.485 0.918 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.787 25.088 41 0.862 1.251 37 14 51 -- -- -- -- -- 51 20 0.830 26.583 42 1.084 1.277 35 20 47 -- -- -- -- -- -- -- -- -- 47 19 0.855 27.438 43 1.238 1.475 37 16 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.889 28.466 44 1.254 1.478 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.919 29.304 45 1.309 1.468 29 12 35 -- -- -- -- -- 6 -- 0 -- -- -- -- -- 35 16 0.949 29.912 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.000 30.467 27 -- -- -- 0 -- 10 -- 10 -- 0 -- -- -- 27 14 1.032 30.930 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.125 31.122 19 -- -- -- -- -- 0 -- 0 -- -- -- -- -- 19 12 1.177 32.465 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.211 33.498 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.258 33.548 7 -- -- -- -- -- -- -- -- -- 7 9 1.291 34.498 3 -- -- -- -- -- 3 8 1.319 35.335 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.352 36.203 6 1.391 37.371 5 1.417 37.876*
| |
| 4 1.419* 37.161 Control Rod Density: % 5.44 3 1.377 34.998 2 1.137 27.482 k-effective: 1.00036 Bottom 1 0.328 8.034 Void Fraction: 0.501 Core Delta-P: psia 19.707 % AXIAL TILT -22.950 -14.638 Core Plate Delta-P: psia 15.161 AVG BOT 8ft/12ft 1.1349 1.0813 Coolant Temp: Deg-F 548.3 In Channel Flow: Mlb/hr 59.40 Active Channel Flow: Mlb/hr 57.22 Total Bypass Flow (%): 12.8 (of total core flow)
| |
| Total Water Rod Flow (%): 3.2 (of total core flow)
| |
| Source Convergence 0.00035 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.478 44 39 18 1.463 0.943 45 27 10 7.85 0.820 49.0 42 25 42 4 7.76 0.809 58.0 42 37 12 5 1.475 43 37 16 1.483 0.930 44 39 18 8.31 0.819 43.6 42 29 10 4 7.87 0.809 57.4 42 11 38 5 1.474 43 37 20 1.497 0.922 44 35 14 7.47 0.801 51.4 42 31 12 5 7.90 0.805 57.1 42 21 12 5 1.473 43 35 18 1.517 0.909 45 29 12 7.45 0.801 51.5 41 39 16 5 7.82 0.800 57.3 41 13 38 5 1.469 44 35 14 1.532 0.901 45 39 22 7.43 0.800 51.7 41 37 14 5 7.85 0.800 57.1 41 37 14 5 1.468 45 29 12 1.536 0.898 43 35 18 7.64 0.799 49.0 42 13 34 5 7.77 0.797 57.3 42 19 44 5 1.465 45 27 10 1.539 0.897 45 31 14 7.45 0.797 51.1 42 33 10 5 7.90 0.797 56.7 42 25 12 5 1.452 45 33 12 1.543 0.895 43 37 20 7.51 0.794 50.1 41 43 24 4 7.70 0.794 57.5 42 33 14 5 1.444 45 31 14 1.550 0.890 45 33 12 7.41 0.791 51.0 42 9 34 5 8.97 0.794 47.0 42 29 10 4 1.441 45 41 20 1.550 0.890 45 35 12 7.40 0.791 51.1 42 11 38 5 10.31 0.792 26.5 45 27 10 4
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.33 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 12,101.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-37 Cycle: 23 Core Average Exposure: MWd/MTU 29258.3 Exposure: MWd/MTU (GWd) 12600.0 (1279.46 )
| |
| Delta E: MWd/MTU, (GWd) 499.0 ( 50.67 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.184 5.577 37 0.704 0.717 3 24 Inlet Subcooling: Btu/lbm -24.17 24 0.410 14.411 38 0.393 0.621 47 16 Flow: Mlb/hr 68.92 ( 89.50 %) 23 0.660 19.892 39 0.420 0.789 17 48 22 0.777 23.429 40 0.483 0.916 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.827 25.526 41 0.861 1.250 37 14 51 -- -- -- -- -- 51 20 0.872 27.045 42 1.084 1.274 35 20 47 -- -- -- -- -- -- -- -- -- 47 19 0.898 27.914 43 1.240 1.473 37 20 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.933 28.961 44 1.256 1.478 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 0.963 29.815 45 1.309 1.465 29 12 35 -- -- -- -- -- 6 -- 0 -- -- -- -- -- 35 16 0.991 30.434 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.041 31.002 27 -- -- -- 0 -- 10 -- 10 -- 0 -- -- -- 27 14 1.070 31.481 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.163 31.673 19 -- -- -- -- -- 0 -- 0 -- -- -- -- -- 19 12 1.210 33.040 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.237 34.087 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.274 34.133 7 -- -- -- -- -- -- -- -- -- 7 9 1.295 35.093 3 -- -- -- -- -- 3 8 1.307 35.939 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.322 36.819 6 1.338 37.998 5 1.339* 38.509*
| |
| 4 1.314 37.789 Control Rod Density: % 5.44 3 1.254 35.603 2 1.028 27.979 k-effective: 1.00048 Bottom 1 0.295 8.188 Void Fraction: 0.489 Core Delta-P: psia 19.879 % AXIAL TILT -19.240 -14.629 Core Plate Delta-P: psia 15.334 AVG BOT 8ft/12ft 1.1168 1.0813 Coolant Temp: Deg-F 548.2 In Channel Flow: Mlb/hr 60.15 Active Channel Flow: Mlb/hr 57.97 Total Bypass Flow (%): 12.7 (of total core flow)
| |
| Total Water Rod Flow (%): 3.2 (of total core flow)
| |
| Source Convergence 0.00030 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.478 44 39 18 1.469 0.940 45 27 10 7.30 0.778 50.8 42 25 12 5 7.45 0.783 58.2 42 11 38 5 1.473 43 37 20 1.485 0.929 44 39 18 7.71 0.767 44.4 42 29 10 4 7.34 0.782 58.8 42 37 12 5 1.473 43 37 16 1.497 0.922 44 35 14 7.16 0.766 51.1 41 39 16 6 7.46 0.777 57.9 42 21 12 5 1.470 43 35 18 1.516 0.910 45 29 12 7.12 0.765 51.5 41 37 14 6 7.40 0.774 58.1 41 13 38 5 1.468 44 35 14 1.528 0.903 45 39 22 7.05 0.763 52.2 42 31 12 5 7.25 0.773 58.8 41 15 40 5 1.465 45 29 12 1.537 0.898 43 35 18 7.23 0.762 49.8 42 13 34 5 7.38 0.773 58.1 42 19 44 5 1.463 45 27 10 1.539 0.897 45 31 14 7.06 0.762 51.8 42 33 10 5 7.46 0.768 57.5 42 25 12 5 1.451 45 33 12 1.542 0.895 43 37 20 7.05 0.759 51.7 42 9 34 5 7.28 0.767 58.3 42 33 14 5 1.443 45 31 14 1.546 0.893 45 35 12 7.02 0.759 52.1 41 43 24 5 7.16 0.764 58.8 42 11 32 5 1.441 45 41 20 1.547 0.892 45 33 12 7.02 0.757 51.8 42 11 38 5 7.38 0.763 57.7 42 43 20 5
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.34 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 12,600.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-38 Cycle: 23 Core Average Exposure: MWd/MTU 29758.2 Exposure: MWd/MTU (GWd) 13100.0 (1330.24 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.191 5.677 37 0.703 0.716 3 24 Inlet Subcooling: Btu/lbm -23.96 24 0.426 14.636 38 0.392 0.620 47 16 Flow: Mlb/hr 69.45 ( 90.20 %) 23 0.690 20.258 39 0.419 0.788 17 48 22 0.813 23.861 40 0.481 0.914 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.865 25.987 41 0.861 1.249 37 14 51 -- -- -- -- -- 51 20 0.913 27.531 42 1.083 1.269 29 10 47 -- -- -- -- -- -- -- -- -- 47 19 0.940 28.415 43 1.240 1.471 37 20 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 0.975 29.481 44 1.259 1.479 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.005 30.351 45 1.311 1.464 29 12 35 -- -- -- -- -- 6 -- 0 -- -- -- -- -- 35 16 1.032 30.980 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.080 31.560 27 -- -- -- 0 -- 10 -- 10 -- 0 -- -- -- 27 14 1.106 32.054 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.196 32.242 19 -- -- -- -- -- 0 -- 0 -- -- -- -- -- 19 12 1.239 33.631 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.257 34.688 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.285 34.725 7 -- -- -- -- -- -- -- -- -- 7 9 1.294* 35.690 3 -- -- -- -- -- 3 8 1.292 36.538 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.289 37.420 6 1.286 38.603 5 1.264 39.109*
| |
| 4 1.218 38.373 Control Rod Density: % 5.44 3 1.145 36.156 2 0.932 28.430 k-effective: 1.00059 Bottom 1 0.267 8.328 Void Fraction: 0.478 Core Delta-P: psia 19.969 % AXIAL TILT -15.678 -14.559 Core Plate Delta-P: psia 15.424 AVG BOT 8ft/12ft 1.0993 1.0811 Coolant Temp: Deg-F 548.1 In Channel Flow: Mlb/hr 60.69 Active Channel Flow: Mlb/hr 58.51 Total Bypass Flow (%): 12.6 (of total core flow)
| |
| Total Water Rod Flow (%): 3.1 (of total core flow)
| |
| Source Convergence 0.00039 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.479 44 39 18 1.465 0.942 45 27 10 6.98 0.745 50.9 42 25 12 6 7.19 0.764 58.7 42 37 12 6 1.471 43 37 20 1.484 0.930 44 39 18 6.88 0.742 51.9 41 39 16 6 7.31 0.761 57.9 42 11 38 6 1.470 43 37 16 1.493 0.924 44 35 14 6.84 0.741 52.3 41 37 14 6 7.27 0.753 57.7 41 13 38 6 1.468 44 35 14 1.513 0.912 45 29 12 6.97 0.737 50.0 42 13 34 6 7.29 0.752 57.6 41 37 14 6 1.467 43 35 18 1.527 0.904 45 39 22 6.76 0.734 52.5 42 31 12 6 7.21 0.752 58.0 42 21 12 6 1.464 45 29 12 1.539 0.897 45 31 14 7.15 0.733 47.2 42 37 18 8 6.99 0.747 58.9 42 19 44 5 1.463 45 27 10 1.540 0.896 43 35 18 7.18 0.732 46.7 42 29 10 5 7.06 0.744 58.3 42 33 14 6 1.451 45 33 12 1.541 0.896 45 35 12 6.82 0.732 51.4 42 11 38 6 7.21 0.743 57.5 42 13 34 6 1.442 45 41 20 1.542 0.895 45 33 12 6.71 0.730 52.6 42 33 10 6 7.06 0.741 58.2 42 25 12 5 1.441 45 31 14 1.542 0.895 43 37 20 6.82 0.729 51.2 42 43 20 6 6.93 0.741 58.9 42 11 32 6
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.35 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 13,100.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-39 Cycle: 23 Core Average Exposure: MWd/MTU 30258.2 Exposure: MWd/MTU (GWd) 13600.0 (1381.01 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.199 5.782 37 0.703 0.715 3 24 Inlet Subcooling: Btu/lbm -23.72 24 0.443 14.870 38 0.391 0.619 47 16 Flow: Mlb/hr 70.07 ( 91.00 %) 23 0.720 20.641 39 0.419 0.788 17 48 22 0.849 24.311 40 0.480 0.914 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.904 26.468 41 0.861 1.247 37 14 51 -- -- -- -- -- 51 20 0.954 28.039 42 1.081 1.269 29 10 47 -- -- -- -- -- -- -- -- -- 47 19 0.983 28.938 43 1.238 1.468 37 16 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.019 30.024 44 1.262 1.479 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.049 30.910 45 1.314 1.464 27 10 35 -- -- -- -- -- 6 -- 0 -- -- -- -- -- 35 16 1.073 31.548 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.119 32.138 27 -- -- -- 0 -- 10 -- 10 -- 0 -- -- -- 27 14 1.141 32.645 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.229 32.827 19 -- -- -- -- -- 0 -- 0 -- -- -- -- -- 19 12 1.265 34.235 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.274 35.299 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.292* 35.322 7 -- -- -- -- -- -- -- -- -- 7 9 1.290 36.286 3 -- -- -- -- -- 3 8 1.274 37.129 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.254 38.007 6 1.233 39.184 5 1.190 39.675*
| |
| 4 1.125 38.913 Control Rod Density: % 5.44 3 1.040 36.659 2 0.841 28.839 k-effective: 1.00069 Bottom 1 0.240 8.453 Void Fraction: 0.467 Core Delta-P: psia 20.089 % AXIAL TILT -12.055 -14.430 Core Plate Delta-P: psia 15.545 AVG BOT 8ft/12ft 1.0814 1.0805 Coolant Temp: Deg-F 547.9 In Channel Flow: Mlb/hr 61.29 Active Channel Flow: Mlb/hr 59.12 Total Bypass Flow (%): 12.5 (of total core flow)
| |
| Total Water Rod Flow (%): 3.1 (of total core flow)
| |
| Source Convergence 0.00034 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.479 44 39 18 1.463 0.943 45 27 10 7.45 0.733 43.2 42 37 18 14 6.90 0.748 59.4 42 37 12 6 1.468 43 37 16 1.482 0.931 44 39 18 7.02 0.731 48.7 41 37 14 9 7.02 0.746 58.7 42 11 38 6 1.467 43 37 20 1.492 0.925 44 35 14 7.06 0.730 48.0 41 39 16 9 7.56 0.739 55.4 41 37 14 10 1.467 44 35 14 1.511 0.913 45 29 12 7.11 0.725 46.8 42 39 20 9 7.00 0.738 58.4 41 13 38 6 1.464 45 27 10 1.527 0.904 45 39 22 6.96 0.724 48.5 42 33 14 9 6.91 0.735 58.7 42 21 12 6 1.464 45 29 12 1.537 0.898 45 35 12 7.04 0.724 47.4 42 25 12 9 6.82 0.733 59.1 42 19 44 6 1.462 43 35 18 1.538 0.897 45 33 12 6.88 0.723 49.6 42 31 12 9 6.93 0.729 58.3 42 13 34 6 1.452 45 33 12 1.541 0.896 45 31 14 7.49 0.722 41.3 42 35 16 14 6.77 0.727 59.0 42 33 14 6 1.443 45 41 20 1.543 0.895 45 41 20 6.57 0.711 52.1 42 11 38 6 8.20 0.727 47.1 42 37 18 14 1.440 45 31 14 1.545 0.893 43 35 18 6.57 0.708 51.9 42 43 20 6 6.67 0.727 59.6 42 11 32 6
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.36 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 13,600.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-40 Cycle: 23 Core Average Exposure: MWd/MTU 30658.2 Exposure: MWd/MTU (GWd) 14000.0 (1421.63 )
| |
| Delta E: MWd/MTU, (GWd) 400.0 ( 40.62 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.205 5.868 37 0.703 0.715 3 24 Inlet Subcooling: Btu/lbm -23.43 24 0.456 15.063 38 0.390 0.618 47 16 Flow: Mlb/hr 70.84 ( 92.00 %) 23 0.743 20.958 39 0.418 0.789 17 48 22 0.877 24.686 40 0.479 0.914 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.935 26.869 41 0.861 1.246 37 14 51 -- -- -- -- -- 51 20 0.988 28.462 42 1.079 1.269 29 10 47 -- -- -- -- -- -- -- -- -- 47 19 1.017 29.374 43 1.236 1.465 37 16 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.055 30.475 44 1.266 1.479 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.084 31.375 45 1.316 1.466 27 10 35 -- -- -- -- -- 6 -- 0 -- -- -- -- -- 35 16 1.106 32.018 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.149 32.615 27 -- -- -- 0 -- 10 -- 10 -- 0 -- -- -- 27 14 1.168 33.131 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.252 33.306 19 -- -- -- -- -- 0 -- 0 -- -- -- -- -- 19 12 1.283 34.727 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.284 35.792 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.295* 35.801 7 -- -- -- -- -- -- -- -- -- 7 9 1.284 36.760 3 -- -- -- -- -- 3 8 1.257 37.596 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.225 38.464 6 1.191 39.631 5 1.133 40.104*
| |
| 4 1.055 39.315 Control Rod Density: % 5.44 3 0.963 37.029 2 0.773 29.136 k-effective: 1.00080 Bottom 1 0.221 8.545 Void Fraction: 0.458 Core Delta-P: psia 20.301 % AXIAL TILT -9.187 -14.287 Core Plate Delta-P: psia 15.757 AVG BOT 8ft/12ft 1.0671 1.0799 Coolant Temp: Deg-F 547.9 In Channel Flow: Mlb/hr 62.02 Active Channel Flow: Mlb/hr 59.85 Total Bypass Flow (%): 12.4 (of total core flow)
| |
| Total Water Rod Flow (%): 3.1 (of total core flow)
| |
| Source Convergence 0.00036 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.479 44 39 18 1.463 0.943 45 27 10 7.58 0.750 43.8 42 37 18 14 7.54 0.748 56.1 41 37 14 10 1.466 44 35 14 1.483 0.931 44 39 18 7.61 0.739 41.9 42 35 16 14 8.38 0.744 47.4 42 37 18 15 1.466 45 27 10 1.495 0.923 44 35 14 7.37 0.738 45.1 42 33 14 14 7.44 0.744 56.3 41 13 16 10 1.465 43 37 16 1.512 0.912 45 29 12 7.44 0.736 43.9 41 37 14 14 6.67 0.735 60.0 42 37 12 6 1.464 45 29 12 1.534 0.900 45 39 22 7.37 0.732 44.3 41 39 16 14 6.80 0.734 59.2 42 11 38 6 1.464 43 37 20 1.536 0.898 45 35 12 7.34 0.728 44.0 42 39 20 14 8.41 0.733 45.4 42 35 16 15 1.457 43 35 18 1.538 0.897 45 33 12 7.24 0.724 44.8 42 31 12 14 8.12 0.731 49.0 42 33 14 14 1.453 45 33 12 1.542 0.895 45 41 20 7.00 0.724 48.0 42 25 12 9 8.55 0.725 42.1 42 35 20 15 1.444 45 41 20 1.545 0.893 44 39 14 7.22 0.717 44.3 42 29 14 14 8.10 0.723 47.9 42 39 20 14 1.439 45 31 14 1.547 0.892 45 31 14 7.62 0.715 38.5 42 35 20 14 6.62 0.722 59.6 42 19 44 6
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.37 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 14,000.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-41 Cycle: 23 Core Average Exposure: MWd/MTU 31058.4 Exposure: MWd/MTU (GWd) 14400.0 (1462.25 )
| |
| Delta E: MWd/MTU, (GWd) 400.0 ( 40.62 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.210 5.957 37 0.703 0.716 3 24 Inlet Subcooling: Btu/lbm -23.15 24 0.469 15.263 38 0.390 0.618 47 16 Flow: Mlb/hr 71.61 ( 93.00 %) 23 0.766 21.286 39 0.418 0.789 17 48 22 0.905 25.073 40 0.478 0.915 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 0.966 27.283 41 0.861 1.244 37 14 51 -- -- -- -- -- 51 20 1.021 28.899 42 1.077 1.269 29 10 47 -- -- -- -- -- -- -- -- -- 47 19 1.052 29.824 43 1.233 1.461 37 16 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.091 30.943 44 1.270 1.478 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.119 31.854 45 1.319 1.468 27 10 35 -- -- -- -- -- 6 -- 0 -- -- -- -- -- 35 16 1.139 32.502 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.179 33.105 27 -- -- -- 0 -- 10 -- 10 -- 0 -- -- -- 27 14 1.194 33.628 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.275 33.794 19 -- -- -- -- -- 0 -- 0 -- -- -- -- -- 19 12 1.299* 35.225 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.292 36.289 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.295 36.280 7 -- -- -- -- -- -- -- -- -- 7 9 1.276 37.232 3 -- -- -- -- -- 3 8 1.237 38.056 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.195 38.910 6 1.147 40.062 5 1.077 40.511*
| |
| 4 0.988 39.692 Control Rod Density: % 5.44 3 0.892 37.371 2 0.712 29.410 k-effective: 1.00077 Bottom 1 0.203 8.629 Void Fraction: 0.449 Core Delta-P: psia 20.516 % AXIAL TILT -6.327 -14.110 Core Plate Delta-P: psia 15.972 AVG BOT 8ft/12ft 1.0528 1.0791 Coolant Temp: Deg-F 547.8 In Channel Flow: Mlb/hr 62.76 Active Channel Flow: Mlb/hr 60.57 Total Bypass Flow (%): 12.4 (of total core flow)
| |
| Total Water Rod Flow (%): 3.0 (of total core flow)
| |
| Source Convergence 0.00034 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.478 44 39 18 1.464 0.943 45 27 10 7.70 0.767 44.5 42 37 18 14 8.54 0.763 48.1 42 37 18 15 1.468 45 27 10 1.487 0.928 44 39 18 7.49 0.756 45.7 42 33 14 14 8.46 0.759 48.6 41 37 14 15 1.464 44 35 14 1.500 0.920 44 35 14 7.57 0.754 44.5 41 37 14 14 8.57 0.753 46.1 42 35 16 15 1.464 45 29 12 1.515 0.911 45 29 12 7.72 0.754 42.6 42 35 16 14 7.41 0.753 57.0 41 13 16 10 1.461 43 37 16 1.536 0.898 45 35 12 7.50 0.750 44.9 41 39 16 14 8.31 0.751 49.2 42 33 14 15 1.459 43 37 20 1.540 0.896 45 33 12 7.47 0.745 44.6 42 39 20 14 8.69 0.742 42.8 42 35 20 15 1.453 45 33 12 1.541 0.895 45 39 22 7.39 0.743 45.4 42 31 12 14 8.26 0.741 48.6 42 29 14 15 1.451 43 35 18 1.543 0.894 45 41 20 7.46 0.740 44.1 42 25 12 14 8.27 0.741 48.3 42 39 20 15 1.445 45 41 20 1.544 0.894 44 39 14 7.34 0.735 44.9 42 29 14 14 8.25 0.737 48.1 42 27 12 14 1.437 45 31 14 1.545 0.893 45 31 10 7.77 0.730 38.7 42 35 20 15 8.19 0.737 48.8 42 31 12 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.38 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 14,400.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-42 Cycle: 23 Core Average Exposure: MWd/MTU 31508.2 Exposure: MWd/MTU (GWd) 14850.0 (1507.94 )
| |
| Delta E: MWd/MTU, (GWd) 450.0 ( 45.70 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.217 6.060 37 0.704 0.716 3 24 Inlet Subcooling: Btu/lbm -22.74 24 0.485 15.494 38 0.389 0.617 47 16 Flow: Mlb/hr 72.76 ( 94.50 %) 23 0.794 21.667 39 0.418 0.791 17 48 22 0.940 25.524 40 0.478 0.916 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.004 27.765 41 0.862 1.241 37 14 51 -- -- -- -- -- 51 20 1.062 29.409 42 1.074 1.269 29 10 47 -- -- -- -- -- -- -- -- -- 47 19 1.094 30.350 43 1.228 1.456 37 16 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.133 31.487 44 1.275 1.476 39 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.160 32.413 45 1.323 1.471 27 10 35 -- -- -- -- -- 6 -- 0 -- -- -- -- -- 35 16 1.176 33.064 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.213 33.671 27 -- -- -- 0 -- 10 -- 10 -- 0 -- -- -- 27 14 1.222 34.199 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.297 34.352 19 -- -- -- -- -- 0 -- 0 -- -- -- -- -- 19 12 1.314* 35.793 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.296 36.851 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.292 36.819 7 -- -- -- -- -- -- -- -- -- 7 9 1.262 37.759 3 -- -- -- -- -- 3 8 1.213 38.564 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.159 39.398 6 1.097 40.528 5 1.013 40.945*
| |
| 4 0.914 40.086 Control Rod Density: % 5.44 3 0.814 37.724 2 0.646 29.691 k-effective: 1.00074 Bottom 1 0.185 8.715 Void Fraction: 0.438 Core Delta-P: psia 20.874 % AXIAL TILT -2.973 -13.871 Core Plate Delta-P: psia 16.330 AVG BOT 8ft/12ft 1.0357 1.0780 Coolant Temp: Deg-F 547.7 In Channel Flow: Mlb/hr 63.84 Active Channel Flow: Mlb/hr 61.65 Total Bypass Flow (%): 12.3 (of total core flow)
| |
| Total Water Rod Flow (%): 3.0 (of total core flow)
| |
| Source Convergence 0.00049 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.476 44 39 18 1.468 0.940 45 27 10 7.87 0.786 44.7 42 37 18 15 8.70 0.784 48.9 42 37 18 15 1.471 45 27 10 1.496 0.923 44 39 18 7.68 0.776 45.9 42 33 14 15 8.66 0.783 49.4 41 37 14 15 1.463 45 29 12 1.509 0.915 44 35 14 7.91 0.774 42.7 42 35 16 15 8.45 0.774 50.9 41 39 16 15 1.461 44 35 14 1.522 0.907 45 29 12 7.70 0.773 45.3 41 37 14 14 8.50 0.773 50.0 42 33 14 15 1.456 43 37 16 1.539 0.897 45 35 12 7.63 0.770 45.6 41 39 16 14 8.74 0.773 46.9 42 35 16 15 1.453 45 33 12 1.544 0.894 45 31 10 7.60 0.764 45.4 42 39 20 14 8.45 0.763 49.4 42 29 14 15 1.452 43 37 20 1.546 0.893 45 33 12 7.54 0.764 46.1 42 31 12 14 8.47 0.763 49.0 42 39 20 15 1.446 45 41 20 1.546 0.893 44 39 14 7.62 0.762 44.9 42 25 12 14 8.40 0.761 49.6 42 31 12 15 1.444 43 35 18 1.547 0.892 45 41 20 7.54 0.755 45.0 42 29 14 15 8.49 0.761 48.4 42 27 12 15 1.434 45 31 14 1.549 0.891 45 39 22 7.90 0.747 39.4 42 35 20 15 8.83 0.759 43.6 42 35 20 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.39 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 14,850.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-43 Cycle: 23 Core Average Exposure: MWd/MTU 31509.2 Exposure: MWd/MTU (GWd) 14851.0 (1508.04 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.225 6.060 37 0.685 0.700 3 24 Inlet Subcooling: Btu/lbm -22.87 24 0.501 15.494 38 0.376 0.601 47 16 Flow: Mlb/hr 72.38 ( 94.00 %) 23 0.817 21.668 39 0.403 0.759 17 48 22 0.957 25.525 40 0.461 0.892 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.007 27.766 41 0.833 1.197 39 38 51 -- -- -- -- -- 51 20 1.060 29.411 42 1.108 1.295 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 1.095 30.351 43 1.383 1.537 25 26 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.135 31.489 44 1.223 1.408 39 18 39 -- -- -- -- 6 -- 6 -- -- -- -- 39 17 1.162 32.414 45 1.236 1.371 41 18 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.177 33.066 31 -- -- -- 6 -- -- -- -- -- 0 -- -- -- 31 15 1.211 33.672 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.218 34.201 23 -- -- -- 0 -- -- -- -- -- 6 -- -- -- 23 13 1.291 34.353 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.305* 35.794 15 -- -- -- -- 6 -- 0 -- -- -- -- 15 11 1.286 36.852 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.280 36.821 7 -- -- -- -- -- -- -- -- -- 7 9 1.250 37.760 3 -- -- -- -- -- 3 8 1.202 38.565 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.150 39.399 6 1.092 40.529 5 1.011 40.945*
| |
| 4 0.916 40.087 Control Rod Density: % 5.38 3 0.818 37.725 2 0.650 29.692 k-effective: 1.00043 Bottom 1 0.186 8.716 Void Fraction: 0.437 Core Delta-P: psia 20.716 % AXIAL TILT -2.442 -13.871 Core Plate Delta-P: psia 16.174 AVG BOT 8ft/12ft 1.0318 1.0780 Coolant Temp: Deg-F 547.7 In Channel Flow: Mlb/hr 63.50 Active Channel Flow: Mlb/hr 61.32 Total Bypass Flow (%): 12.3 (of total core flow)
| |
| Total Water Rod Flow (%): 3.0 (of total core flow)
| |
| Source Convergence 0.00045 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.537 43 25 26 1.454 0.949 43 27 28 8.44 0.849 45.5 42 27 26 15 9.19 0.838 50.3 42 29 28 15 1.529 43 29 24 1.479 0.933 43 21 28 8.39 0.849 46.0 42 29 26 15 9.08 0.830 50.6 42 27 30 15 1.524 43 31 26 1.481 0.932 43 29 30 8.31 0.842 46.2 42 27 24 15 9.13 0.828 49.7 42 27 26 15 1.517 43 25 32 1.486 0.929 43 29 20 8.16 0.824 45.7 42 31 24 15 9.03 0.822 50.0 42 29 22 15 1.512 43 31 22 1.490 0.926 43 27 22 8.14 0.823 45.9 42 29 22 15 9.01 0.819 50.0 42 31 24 15 1.490 43 23 34 1.515 0.911 43 21 32 7.95 0.803 45.7 42 33 26 15 8.84 0.800 49.4 42 27 20 15 1.476 43 33 24 1.525 0.905 43 19 30 7.98 0.801 45.3 42 27 20 15 9.05 0.799 46.7 42 31 20 15 1.474 43 33 20 1.556 0.887 43 33 20 8.18 0.799 42.6 42 31 20 15 8.86 0.798 48.9 42 19 28 15 1.439 43 35 18 1.580 0.873 44 39 18 7.92 0.799 45.7 42 33 22 15 8.76 0.797 50.0 42 33 22 15 1.408 44 39 18 1.586 0.870 43 31 18 7.71 0.766 44.3 42 33 18 15 8.60 0.771 48.4 42 33 18 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.40 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 14,851.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-44 Cycle: 23 Core Average Exposure: MWd/MTU 31858.3 Exposure: MWd/MTU (GWd) 15200.0 (1543.48 )
| |
| Delta E: MWd/MTU, (GWd) 349.0 ( 35.44 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.231 6.146 37 0.687 0.702 3 24 Inlet Subcooling: Btu/lbm -22.21 24 0.516 15.685 38 0.377 0.602 47 16 Flow: Mlb/hr 74.31 ( 96.50 %) 23 0.843 21.982 39 0.404 0.763 17 48 22 0.988 25.893 40 0.462 0.896 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.039 28.155 41 0.836 1.200 39 38 51 -- -- -- -- -- 51 20 1.093 29.820 42 1.103 1.269 27 26 47 -- -- -- -- -- -- -- -- -- 47 19 1.129 30.774 43 1.371 1.509 27 28 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.168 31.926 44 1.231 1.410 39 18 39 -- -- -- -- 6 -- 6 -- -- -- -- 39 17 1.192 32.861 45 1.243 1.376 41 18 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.203 33.514 31 -- -- -- 6 -- -- -- -- -- 0 -- -- -- 31 15 1.234 34.121 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.236 34.651 23 -- -- -- 0 -- -- -- -- -- 6 -- -- -- 23 13 1.304 34.790 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.312* 36.235 15 -- -- -- -- 6 -- 0 -- -- -- -- 15 11 1.286 37.285 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.274 37.233 7 -- -- -- -- -- -- -- -- -- 7 9 1.237 38.160 3 -- -- -- -- -- 3 8 1.183 38.949 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.122 39.765 6 1.053 40.874 5 0.963 41.263*
| |
| 4 0.860 40.373 Control Rod Density: % 5.38 3 0.760 37.979 2 0.601 29.893 k-effective: 1.00037 Bottom 1 0.172 8.778 Void Fraction: 0.427 Core Delta-P: psia 21.415 % AXIAL TILT 0.208 -13.651 Core Plate Delta-P: psia 16.872 AVG BOT 8ft/12ft 1.0174 1.0770 Coolant Temp: Deg-F 547.6 In Channel Flow: Mlb/hr 65.26 Active Channel Flow: Mlb/hr 63.05 Total Bypass Flow (%): 12.2 (of total core flow)
| |
| Total Water Rod Flow (%): 3.0 (of total core flow)
| |
| Source Convergence 0.00020 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.509 43 27 28 1.504 0.918 43 27 28 8.31 0.846 46.6 42 29 26 15 9.10 0.836 51.1 42 29 28 15 1.503 43 23 30 1.522 0.907 43 29 30 8.35 0.846 46.1 42 27 26 15 9.01 0.828 51.2 42 27 30 15 1.498 43 21 28 1.525 0.905 43 21 28 8.22 0.839 46.8 42 27 24 15 9.03 0.824 50.4 42 27 26 15 1.494 43 25 32 1.527 0.903 43 29 20 8.11 0.823 46.3 42 31 24 15 8.97 0.821 50.7 42 29 22 15 1.491 43 21 32 1.534 0.900 43 27 22 8.09 0.823 46.4 42 29 22 15 8.96 0.818 50.4 42 21 30 15 1.474 43 23 34 1.556 0.887 43 21 32 7.92 0.804 46.3 42 33 26 15 9.04 0.803 47.4 42 31 20 15 1.461 43 33 20 1.557 0.886 43 19 30 7.92 0.804 46.3 42 33 22 15 8.81 0.801 50.0 42 27 20 15 1.456 43 33 24 1.590 0.868 44 13 36 7.95 0.804 45.9 42 27 20 15 8.84 0.801 49.6 42 19 28 15 1.433 43 35 18 1.591 0.867 43 19 20 8.17 0.803 43.2 42 31 20 15 8.75 0.801 50.7 42 33 22 15 1.410 44 39 18 1.602 0.861 44 35 14 7.75 0.775 44.8 42 33 18 15 8.65 0.779 49.0 42 33 18 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.41 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 15,200.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-45 Cycle: 23 Core Average Exposure: MWd/MTU 32258.3 Exposure: MWd/MTU (GWd) 15600.0 (1584.10 )
| |
| Delta E: MWd/MTU, (GWd) 400.0 ( 40.62 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.8 Top 25 0.238 6.246 37 0.690 0.705 3 24 Inlet Subcooling: Btu/lbm -21.33 24 0.532 15.911 38 0.377 0.602 47 16 Flow: Mlb/hr 77.00 (100.00 %) 23 0.872 22.354 39 0.405 0.766 17 48 22 1.022 26.330 40 0.463 0.901 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.076 28.616 41 0.839 1.202 39 38 51 -- -- -- -- -- 51 20 1.132 30.304 42 1.099 1.246 21 30 47 -- -- -- -- -- -- -- -- -- 47 19 1.167 31.274 43 1.359 1.482 27 28 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.205 32.443 44 1.239 1.410 39 18 39 -- -- -- -- 6 -- 6 -- -- -- -- 39 17 1.227 33.388 45 1.250 1.382 41 18 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.233 34.039 31 -- -- -- 6 -- -- -- -- -- 0 -- -- -- 31 15 1.259 34.646 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.255 35.175 23 -- -- -- 0 -- -- -- -- -- 6 -- -- -- 23 13 1.318 35.297 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.320* 36.743 15 -- -- -- -- 6 -- 0 -- -- -- -- 15 11 1.286 37.781 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.268 37.704 7 -- -- -- -- -- -- -- -- -- 7 9 1.224 38.614 3 -- -- -- -- -- 3 8 1.161 39.381 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.089 40.172 6 1.009 41.254 5 0.908 41.608*
| |
| 4 0.798 40.679 Control Rod Density: % 5.38 3 0.696 38.247 2 0.548 30.104 k-effective: 1.00048 Bottom 1 0.157 8.843 Void Fraction: 0.415 Core Delta-P: psia 22.439 % AXIAL TILT 3.178 -13.370 Core Plate Delta-P: psia 17.893 AVG BOT 8ft/12ft 1.0013 1.0756 Coolant Temp: Deg-F 547.6 In Channel Flow: Mlb/hr 67.72 Active Channel Flow: Mlb/hr 65.46 Total Bypass Flow (%): 12.0 (of total core flow)
| |
| Total Water Rod Flow (%): 2.9 (of total core flow)
| |
| Source Convergence 0.00050 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.482 43 27 28 1.560 0.885 43 27 28 8.25 0.845 47.1 42 23 28 15 9.03 0.835 51.8 42 29 28 15 1.478 43 23 30 1.566 0.881 43 29 30 8.27 0.844 46.8 42 27 26 15 8.95 0.829 52.0 42 27 30 15 1.474 43 21 28 1.575 0.876 43 21 28 8.16 0.839 47.5 42 27 24 15 8.95 0.822 51.1 42 27 26 15 1.472 43 21 32 1.577 0.875 43 29 20 7.98 0.826 48.0 42 21 24 15 8.92 0.822 51.4 42 29 22 15 1.472 43 25 32 1.583 0.872 43 27 22 7.96 0.824 48.1 42 23 22 15 8.94 0.822 51.2 42 21 30 15 1.457 43 23 34 1.595 0.865 43 19 30 7.91 0.809 46.9 42 33 22 15 9.02 0.807 48.1 42 31 20 15 1.446 43 33 20 1.597 0.864 43 21 32 7.97 0.808 46.2 42 19 26 15 8.84 0.806 50.3 42 19 28 15 1.436 43 33 24 1.601 0.862 44 13 36 8.16 0.808 43.8 42 31 20 15 8.74 0.805 51.4 42 33 22 15 1.425 43 35 18 1.622 0.851 44 35 14 7.93 0.807 46.6 42 27 20 15 8.78 0.804 50.8 42 27 20 15 1.410 44 39 18 1.625 0.849 43 19 20 7.80 0.785 45.5 42 33 18 15 8.69 0.788 49.7 42 33 18 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.42 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 15,600.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-46 Cycle: 23 Core Average Exposure: MWd/MTU 32658.3 Exposure: MWd/MTU (GWd) 16000.0 (1624.72 )
| |
| Delta E: MWd/MTU, (GWd) 400.0 ( 40.62 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.8 Top 25 0.245 6.350 37 0.692 0.708 3 24 Inlet Subcooling: Btu/lbm -20.29 24 0.549 16.144 38 0.377 0.602 47 16 Flow: Mlb/hr 80.46 (104.50 %) 23 0.904 22.740 39 0.405 0.770 17 48 22 1.059 26.782 40 0.463 0.906 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.116 29.093 41 0.842 1.204 39 38 51 -- -- -- -- -- 51 20 1.174 30.806 42 1.094 1.229 31 20 47 -- -- -- -- -- -- -- -- -- 47 19 1.208 31.791 43 1.346 1.456 27 28 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.244 32.977 44 1.248 1.410 39 18 39 -- -- -- -- 6 -- 6 -- -- -- -- 39 17 1.261 33.930 45 1.258 1.386 41 18 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.261 34.577 31 -- -- -- 6 -- -- -- -- -- 0 -- -- -- 31 15 1.283 35.181 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.272 35.707 23 -- -- -- 0 -- -- -- -- -- 6 -- -- -- 23 13 1.330* 35.808 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.324 37.253 15 -- -- -- -- 6 -- 0 -- -- -- -- 15 11 1.281 38.276 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.257 38.171 7 -- -- -- -- -- -- -- -- -- 7 9 1.208 39.063 3 -- -- -- -- -- 3 8 1.137 39.805 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.054 40.568 6 0.963 41.618 5 0.854 41.933*
| |
| 4 0.739 40.962 Control Rod Density: % 5.38 3 0.637 38.493 2 0.500 30.297 k-effective: 1.00060 Bottom 1 0.143 8.902 Void Fraction: 0.401 Core Delta-P: psia 23.814 % AXIAL TILT 6.256 -13.058 Core Plate Delta-P: psia 19.267 AVG BOT 8ft/12ft 0.9841 1.0741 Coolant Temp: Deg-F 547.6 In Channel Flow: Mlb/hr 70.88 Active Channel Flow: Mlb/hr 68.56 Total Bypass Flow (%): 11.9 (of total core flow)
| |
| Total Water Rod Flow (%): 2.9 (of total core flow)
| |
| Source Convergence 0.00046 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.456 43 27 28 1.609 0.858 43 27 28 8.38 0.844 45.5 42 27 26 17 9.15 0.834 50.3 42 29 28 17 1.455 43 21 32 1.613 0.856 43 29 30 8.34 0.844 45.9 42 23 26 17 9.08 0.830 50.6 42 27 30 17 1.455 43 23 30 1.616 0.854 44 13 36 8.27 0.839 46.2 42 25 24 17 8.90 0.823 51.9 42 21 30 15 1.451 43 21 28 1.621 0.851 43 21 28 8.11 0.829 46.9 42 31 30 17 9.06 0.821 49.7 42 27 26 17 1.450 43 25 32 1.625 0.849 43 29 20 8.13 0.828 46.6 42 23 22 17 8.85 0.821 52.2 42 29 22 15 1.441 43 23 34 1.632 0.846 43 27 22 7.89 0.812 47.6 42 33 22 15 8.89 0.811 50.4 42 21 20 15 1.437 43 19 34 1.634 0.844 43 19 30 7.94 0.811 46.9 42 19 26 15 8.86 0.809 50.4 42 19 22 15 1.422 43 17 36 1.642 0.840 43 21 32 8.13 0.811 44.5 42 31 20 15 8.81 0.808 51.0 42 19 28 15 1.420 43 19 30 1.648 0.838 44 35 14 8.09 0.810 45.0 42 25 20 17 8.76 0.808 51.5 41 37 14 15 1.410 44 39 18 1.654 0.834 44 39 40 7.83 0.798 46.6 42 37 18 15 8.73 0.805 51.5 42 27 20 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.43 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 16,000.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-47 Cycle: 23 Core Average Exposure: MWd/MTU 32659.2 Exposure: MWd/MTU (GWd) 16001.0 (1624.82 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.274 6.350 37 0.690 0.709 3 24 Inlet Subcooling: Btu/lbm -24.15 24 0.608 16.144 38 0.377 0.603 47 16 Flow: Mlb/hr 68.92 ( 89.50 %) 23 0.997 22.741 39 0.403 0.755 17 48 22 1.168 26.783 40 0.461 0.897 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.231 29.094 41 0.835 1.192 37 14 51 -- -- -- -- -- 51 20 1.257 30.808 42 1.105 1.248 35 20 47 -- -- -- -- -- -- -- -- -- 47 19 1.257 31.793 43 1.357 1.451 31 22 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.266 32.978 44 1.229 1.408 39 18 39 -- -- -- -- 8 -- 8 -- -- -- -- 39 17 1.261 33.931 45 1.253 1.381 43 26 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.244 34.579 31 -- -- -- 10 -- -- -- -- -- 8 -- -- -- 31 15 1.250 35.182 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.227 35.708 23 -- -- -- 8 -- -- -- -- -- 10 -- -- -- 23 13 1.273* 35.809 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.260 37.254 15 -- -- -- -- 8 -- 8 -- -- -- -- 15 11 1.217 38.277 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.193 38.172 7 -- -- -- -- -- -- -- -- -- 7 9 1.147 39.064 3 -- -- -- -- -- 3 8 1.084 39.806 2 6 10 14 18 22 26 30 34 38 42 46 50 7 1.012 40.569 6 0.932 41.619 5 0.835 41.934*
| |
| 4 0.730 40.963 Control Rod Density: % 4.81 3 0.634 38.493 2 0.499 30.298 k-effective: 1.00024 Bottom 1 0.143 8.902 Void Fraction: 0.415 Core Delta-P: psia 18.964 % AXIAL TILT 9.925 -13.057 Core Plate Delta-P: psia 14.429 AVG BOT 8ft/12ft 0.9512 1.0741 Coolant Temp: Deg-F 547.1 In Channel Flow: Mlb/hr 60.56 Active Channel Flow: Mlb/hr 58.52 Total Bypass Flow (%): 12.1 (of total core flow)
| |
| Total Water Rod Flow (%): 3.0 (of total core flow)
| |
| Source Convergence 0.00022 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.451 43 31 22 1.477 0.935 43 29 20 8.48 0.851 45.1 42 29 26 18 9.28 0.840 49.5 42 29 28 18 1.446 43 33 20 1.478 0.934 43 21 28 8.47 0.847 44.9 42 27 26 18 9.85 0.833 41.7 42 37 22 21 1.445 43 31 26 1.481 0.932 43 27 22 8.42 0.846 45.3 42 27 24 18 9.19 0.832 49.5 42 25 24 18 1.444 43 25 26 1.482 0.931 44 39 18 8.41 0.841 44.9 42 31 24 18 9.23 0.832 49.1 42 29 22 18 1.444 43 29 24 1.488 0.927 43 27 28 8.37 0.838 45.0 42 29 22 18 9.21 0.830 49.1 42 31 24 18 1.441 43 27 22 1.491 0.925 43 29 30 8.40 0.834 44.1 42 33 22 18 9.24 0.827 48.2 42 33 22 18 1.440 43 29 20 1.496 0.922 43 33 20 8.34 0.831 44.5 42 33 26 18 9.15 0.825 49.1 42 27 26 18 1.427 43 33 24 1.496 0.922 43 21 22 8.55 0.826 41.5 42 31 20 18 9.41 0.821 45.5 42 31 20 18 1.427 43 35 18 1.502 0.919 43 19 30 8.68 0.825 39.9 42 37 22 20 9.14 0.820 48.6 42 33 26 18 1.408 44 39 18 1.506 0.916 44 35 14 8.30 0.823 44.0 42 27 20 18 9.17 0.818 48.0 42 27 20 18
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.44 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 16,001.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-48 Cycle: 23 Core Average Exposure: MWd/MTU 33158.2 Exposure: MWd/MTU (GWd) 16500.0 (1675.49 )
| |
| Delta E: MWd/MTU, (GWd) 499.0 ( 50.67 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.282 6.499 37 0.693 0.713 3 24 Inlet Subcooling: Btu/lbm -22.34 24 0.627 16.476 38 0.377 0.602 47 16 Flow: Mlb/hr 73.92 ( 96.00 %) 23 1.033 23.291 39 0.404 0.760 17 48 22 1.211 27.427 40 0.461 0.904 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.279 29.776 41 0.838 1.194 39 38 51 -- -- -- -- -- 51 20 1.305 31.504 42 1.099 1.233 35 20 47 -- -- -- -- -- -- -- -- -- 47 19 1.302 32.488 43 1.341 1.425 33 20 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.308* 33.677 44 1.240 1.406 39 18 39 -- -- -- -- 8 -- 8 -- -- -- -- 39 17 1.298 34.626 45 1.263 1.390 43 26 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.274 35.256 31 -- -- -- 10 -- -- -- -- -- 8 -- -- -- 31 15 1.275 35.845 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.245 36.357 23 -- -- -- 8 -- -- -- -- -- 10 -- -- -- 23 13 1.286 36.425 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.266 37.863 15 -- -- -- -- 8 -- 8 -- -- -- -- 15 11 1.214 38.862 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.183 38.721 7 -- -- -- -- -- -- -- -- -- 7 9 1.131 39.588 3 -- -- -- -- -- 3 8 1.057 40.299 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.973 41.025 6 0.881 42.036 5 0.772 42.303*
| |
| 4 0.661 41.283 Control Rod Density: % 4.81 3 0.566 38.769 2 0.444 30.515 k-effective: 1.00035 Bottom 1 0.127 8.969 Void Fraction: 0.397 Core Delta-P: psia 20.834 % AXIAL TILT 13.340 -12.572 Core Plate Delta-P: psia 16.296 AVG BOT 8ft/12ft 0.9318 1.0716 Coolant Temp: Deg-F 547.2 In Channel Flow: Mlb/hr 65.10 Active Channel Flow: Mlb/hr 62.95 Total Bypass Flow (%): 11.9 (of total core flow)
| |
| Total Water Rod Flow (%): 2.9 (of total core flow)
| |
| Source Convergence 0.00047 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.425 43 33 20 1.533 0.900 44 39 18 8.42 0.852 46.0 42 29 26 18 10.03 0.856 42.7 42 37 22 21 1.422 43 31 22 1.545 0.893 45 43 26 8.41 0.849 45.8 42 27 26 18 9.23 0.842 50.4 42 29 28 18 1.416 43 21 28 1.548 0.892 43 21 28 8.84 0.848 40.8 42 37 22 20 9.91 0.842 42.2 42 39 24 21 1.414 43 35 18 1.549 0.891 43 29 20 8.36 0.848 46.2 42 27 24 18 9.20 0.836 49.9 42 29 22 18 1.414 43 29 20 1.551 0.890 44 35 14 8.37 0.845 45.8 42 31 24 18 9.15 0.836 50.5 42 25 24 18 1.410 43 23 30 1.554 0.888 43 27 22 8.30 0.844 46.5 42 23 22 18 9.12 0.835 50.7 42 21 24 18 1.410 43 25 26 1.560 0.885 43 19 20 8.42 0.843 45.0 42 33 22 18 9.24 0.834 49.2 42 33 22 18 1.409 43 27 22 1.561 0.884 43 21 22 8.33 0.837 45.4 42 33 26 18 9.61 0.832 44.4 42 35 24 20 1.406 44 39 18 1.563 0.883 43 19 30 8.75 0.836 40.4 42 35 24 20 9.42 0.830 46.4 42 31 20 18 1.401 43 19 30 1.567 0.881 44 39 14 8.57 0.835 42.4 42 31 20 18 9.23 0.829 48.6 42 19 28 18
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.45 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 16,500.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-49 Cycle: 23 Core Average Exposure: MWd/MTU 33658.3 Exposure: MWd/MTU (GWd) 17000.0 (1726.26 )
| |
| Delta E: MWd/MTU, (GWd) 500.0 ( 50.77 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.8 Top 25 0.290 6.652 37 0.695 0.717 3 24 Inlet Subcooling: Btu/lbm -20.29 24 0.648 16.819 38 0.376 0.600 47 16 Flow: Mlb/hr 80.46 (104.50 %) 23 1.072 23.862 39 0.404 0.764 17 48 22 1.257 28.097 40 0.461 0.912 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.330 30.486 41 0.842 1.198 13 38 51 -- -- -- -- -- 51 20 1.357* 32.228 42 1.092 1.218 35 20 47 -- -- -- -- -- -- -- -- -- 47 19 1.350 33.210 43 1.324 1.404 19 34 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.350 34.401 44 1.253 1.405 13 36 39 -- -- -- -- 8 -- 8 -- -- -- -- 39 17 1.333 35.343 45 1.274 1.400 43 26 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.302 35.951 31 -- -- -- 10 -- -- -- -- -- 8 -- -- -- 31 15 1.297 36.521 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.260 37.016 23 -- -- -- 8 -- -- -- -- -- 10 -- -- -- 23 13 1.295 37.047 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.268 38.474 15 -- -- -- -- 8 -- 8 -- -- -- -- 15 11 1.208 39.446 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.171 39.266 7 -- -- -- -- -- -- -- -- -- 7 9 1.112 40.105 3 -- -- -- -- -- 3 8 1.027 40.779 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.930 41.464 6 0.826 42.430 5 0.709 42.645*
| |
| 4 0.596 41.572 Control Rod Density: % 4.81 3 0.505 39.016 2 0.394 30.707 k-effective: 1.00059 Bottom 1 0.113 9.029 Void Fraction: 0.377 Core Delta-P: psia 23.443 % AXIAL TILT 16.831 -12.049 Core Plate Delta-P: psia 18.901 AVG BOT 8ft/12ft 0.9113 1.0688 Coolant Temp: Deg-F 547.3 In Channel Flow: Mlb/hr 71.03 Active Channel Flow: Mlb/hr 68.76 Total Bypass Flow (%): 11.7 (of total core flow)
| |
| Total Water Rod Flow (%): 2.8 (of total core flow)
| |
| Source Convergence 0.00034 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.405 44 13 36 1.574 0.889 44 13 36 9.00 0.872 41.8 42 37 22 20 10.21 0.879 43.7 42 37 22 21 1.404 43 19 34 1.582 0.885 45 43 28 9.12 0.858 38.9 42 39 24 21 10.13 0.867 43.2 42 39 24 21 1.404 43 17 36 1.600 0.875 44 35 14 8.58 0.855 44.5 42 33 22 19 9.72 0.848 45.4 42 35 24 20 1.400 45 43 26 1.601 0.875 45 11 36 8.37 0.855 46.9 42 23 26 18 9.52 0.846 47.5 42 33 22 20 1.398 43 21 32 1.609 0.870 45 43 22 8.86 0.854 41.3 42 35 24 20 10.10 0.846 40.5 42 35 20 20 1.390 43 15 38 1.613 0.868 44 39 14 8.31 0.853 47.4 42 21 24 18 9.17 0.844 51.4 42 29 28 18 1.387 45 41 18 1.619 0.865 45 27 10 8.29 0.851 47.4 42 23 22 18 9.11 0.841 51.7 42 21 24 18 1.387 43 21 28 1.621 0.864 43 19 20 8.30 0.850 47.1 42 25 24 18 9.36 0.840 48.6 42 21 20 18 1.387 43 29 20 1.622 0.863 45 41 20 8.33 0.849 46.6 42 27 26 18 9.17 0.840 50.8 42 29 22 18 1.380 43 19 30 1.622 0.863 43 21 28 8.40 0.845 45.4 42 19 28 18 9.26 0.839 49.6 42 19 28 18
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.46 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 17,000.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-50 Cycle: 23 Core Average Exposure: MWd/MTU 33659.3 Exposure: MWd/MTU (GWd) 17001.0 (1726.36 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.270 6.652 37 0.698 0.724 3 24 Inlet Subcooling: Btu/lbm -22.73 24 0.601 16.820 38 0.378 0.600 47 16 Flow: Mlb/hr 72.76 ( 94.50 %) 23 0.991 23.863 39 0.406 0.769 17 48 22 1.164 28.099 40 0.464 0.916 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.239 30.487 41 0.845 1.216 9 30 51 -- -- -- -- -- 51 20 1.290 32.230 42 1.085 1.234 41 22 47 -- -- -- -- -- -- -- -- -- 47 19 1.304 33.211 43 1.261 1.397 33 16 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.321* 34.402 44 1.263 1.424 13 36 39 -- -- -- -- -- 10 -- -- -- -- -- 39 17 1.319 35.344 45 1.320 1.442 43 26 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.301 35.953 31 -- -- -- -- 8 -- -- -- 6 -- -- -- -- 31 15 1.304 36.523 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.272 37.017 23 -- -- -- -- 6 -- -- -- 8 -- -- -- -- 23 13 1.309 37.049 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.283 38.475 15 -- -- -- -- -- 10 -- -- -- -- -- 15 11 1.225 39.448 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.192 39.267 7 -- -- -- -- -- -- -- -- -- 7 9 1.135 40.106 3 -- -- -- -- -- 3 8 1.057 40.780 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.970 41.464 6 0.877 42.430 5 0.770 42.646*
| |
| 4 0.661 41.573 Control Rod Density: % 3.65 3 0.568 39.017 2 0.447 30.708 k-effective: 1.00030 Bottom 1 0.129 9.029 Void Fraction: 0.400 Core Delta-P: psia 20.391 % AXIAL TILT 12.932 -12.048 Core Plate Delta-P: psia 15.858 AVG BOT 8ft/12ft 0.9402 1.0688 Coolant Temp: Deg-F 547.1 In Channel Flow: Mlb/hr 64.05 Active Channel Flow: Mlb/hr 61.93 Total Bypass Flow (%): 12.0 (of total core flow)
| |
| Total Water Rod Flow (%): 2.9 (of total core flow)
| |
| Source Convergence 0.00033 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.442 45 43 26 1.494 0.937 45 43 28 8.82 0.841 40.2 42 27 16 21 9.78 0.843 44.0 42 27 16 21 1.434 45 41 24 1.515 0.924 45 31 14 8.20 0.835 46.6 42 33 14 17 9.19 0.832 49.5 41 37 14 17 1.424 44 13 36 1.521 0.921 44 13 36 8.36 0.823 43.4 42 35 16 17 8.64 0.828 54.6 41 39 16 15 1.423 45 41 20 1.521 0.920 45 11 30 8.13 0.822 46.0 42 37 18 17 9.00 0.825 50.9 42 33 14 17 1.418 45 39 22 1.526 0.917 45 13 28 8.23 0.820 44.6 41 37 14 17 8.83 0.817 52.0 41 43 24 15 1.416 45 13 28 1.533 0.913 44 35 14 8.21 0.818 44.5 42 33 18 18 9.16 0.816 47.6 42 35 16 17 1.413 45 31 14 1.538 0.910 45 13 32 8.22 0.816 44.1 42 21 16 18 9.46 0.816 44.0 42 29 14 20 1.413 44 35 14 1.541 0.908 45 35 12 7.83 0.816 48.8 41 13 16 15 8.95 0.815 50.2 42 37 18 17 1.407 45 33 12 1.544 0.907 45 43 22 7.89 0.812 47.6 42 13 34 15 9.05 0.813 48.7 42 33 18 18 1.401 45 41 18 1.545 0.906 45 27 10 7.92 0.811 47.2 42 41 26 15 8.76 0.812 52.2 42 13 20 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.47 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 17,001.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-51 Cycle: 23 Core Average Exposure: MWd/MTU 34158.3 Exposure: MWd/MTU (GWd) 17500.0 (1777.03 )
| |
| Delta E: MWd/MTU, (GWd) 499.0 ( 50.67 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.8 Top 25 0.279 6.799 37 0.699 0.727 3 24 Inlet Subcooling: Btu/lbm -20.29 24 0.624 17.149 38 0.376 0.596 47 16 Flow: Mlb/hr 80.46 (104.50 %) 23 1.034 24.412 39 0.405 0.773 17 48 22 1.214 28.743 40 0.463 0.922 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.293 31.175 41 0.848 1.227 9 30 51 -- -- -- -- -- 51 20 1.344 32.945 42 1.080 1.232 41 22 47 -- -- -- -- -- -- -- -- -- 47 19 1.353 33.933 43 1.249 1.400 15 38 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.365* 35.132 44 1.272 1.431 13 36 39 -- -- -- -- -- 10 -- -- -- -- -- 39 17 1.355 36.070 45 1.329 1.452 9 28 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.328 36.660 31 -- -- -- -- 8 -- -- -- 6 -- -- -- -- 31 15 1.325 37.213 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.286 37.689 23 -- -- -- -- 6 -- -- -- 8 -- -- -- -- 23 13 1.316 37.681 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.283 39.093 15 -- -- -- -- -- 10 -- -- -- -- -- 15 11 1.218 40.036 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.178 39.814 7 -- -- -- -- -- -- -- -- -- 7 9 1.114 40.624 3 -- -- -- -- -- 3 8 1.025 41.259 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.926 41.901 6 0.822 42.821 5 0.706 42.985*
| |
| 4 0.595 41.862 Control Rod Density: % 3.65 3 0.506 39.264 2 0.396 30.902 k-effective: 1.00034 Bottom 1 0.114 9.089 Void Fraction: 0.377 Core Delta-P: psia 23.461 % AXIAL TILT 16.535 -11.548 Core Plate Delta-P: psia 18.923 AVG BOT 8ft/12ft 0.9186 1.0663 Coolant Temp: Deg-F 547.3 In Channel Flow: Mlb/hr 71.03 Active Channel Flow: Mlb/hr 68.75 Total Bypass Flow (%): 11.7 (of total core flow)
| |
| Total Water Rod Flow (%): 2.8 (of total core flow)
| |
| Source Convergence 0.00048 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.452 45 9 28 1.539 0.910 45 9 26 9.02 0.868 41.1 42 27 16 21 10.00 0.871 45.0 42 27 16 21 1.440 45 11 30 1.570 0.892 44 13 36 8.38 0.856 46.8 42 33 14 18 8.94 0.865 55.1 41 13 16 15 1.431 44 13 36 1.571 0.891 45 11 30 8.40 0.845 45.4 41 37 14 17 8.87 0.861 55.2 41 37 40 15 1.430 45 11 34 1.578 0.887 45 13 28 8.60 0.844 43.0 42 35 16 18 9.22 0.849 51.3 42 19 14 17 1.422 45 13 32 1.582 0.885 45 21 14 8.28 0.843 46.5 41 13 16 17 9.74 0.847 45.0 42 29 14 20 1.422 45 13 28 1.590 0.880 45 27 44 8.24 0.841 46.8 42 37 18 17 9.05 0.845 52.9 41 43 24 15 1.413 44 17 40 1.592 0.879 45 11 36 8.75 0.841 40.9 42 29 14 20 9.05 0.838 52.0 42 11 28 15 1.412 45 11 36 1.592 0.879 44 17 40 8.31 0.840 45.9 42 13 34 17 9.44 0.837 47.2 42 35 16 18 1.408 45 9 32 1.593 0.879 45 13 32 8.37 0.838 45.0 42 21 16 18 9.17 0.836 50.2 42 13 20 17 1.407 45 31 14 1.597 0.877 45 9 32 8.32 0.838 45.5 42 41 26 17 9.08 0.834 51.1 42 37 18 17
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.48 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 17,500.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-52 Cycle: 23 Core Average Exposure: MWd/MTU 34159.3 Exposure: MWd/MTU (GWd) 17501.0 (1777.14 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.260 6.799 37 0.684 0.707 3 24 Inlet Subcooling: Btu/lbm -22.20 24 0.579 17.150 38 0.371 0.584 37 48 Flow: Mlb/hr 74.31 ( 96.50 %) 23 0.956 24.413 39 0.400 0.770 17 48 22 1.123 28.744 40 0.456 0.896 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.202 31.177 41 0.835 1.189 9 24 51 -- -- -- -- -- 51 20 1.270 32.947 42 1.089 1.254 31 16 47 -- -- -- -- -- -- -- -- -- 47 19 1.305 33.935 43 1.256 1.450 29 16 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.335 35.133 44 1.257 1.406 17 40 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.341* 36.072 45 1.337 1.476 27 14 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.328 36.662 31 -- -- -- -- 6 -- -- -- 6 -- -- -- -- 31 15 1.333 37.214 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.299 37.690 23 -- -- -- -- 6 -- -- -- 6 -- -- -- -- 23 13 1.333 37.682 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.301 39.094 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.237 40.037 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.199 39.815 7 -- -- -- -- -- -- -- -- -- 7 9 1.138 40.625 3 -- -- -- -- -- 3 8 1.055 41.260 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.965 41.901 6 0.871 42.822 5 0.764 42.986*
| |
| 4 0.658 41.863 Control Rod Density: % 2.55 3 0.568 39.264 2 0.449 30.902 k-effective: 1.00017 Bottom 1 0.130 9.089 Void Fraction: 0.397 Core Delta-P: psia 21.034 % AXIAL TILT 12.654 -11.547 Core Plate Delta-P: psia 16.504 AVG BOT 8ft/12ft 0.9475 1.0663 Coolant Temp: Deg-F 547.2 In Channel Flow: Mlb/hr 65.42 Active Channel Flow: Mlb/hr 63.26 Total Bypass Flow (%): 12.0 (of total core flow)
| |
| Total Water Rod Flow (%): 2.9 (of total core flow)
| |
| Source Convergence 0.00032 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.476 45 27 14 1.473 0.950 45 27 44 8.69 0.874 45.4 42 29 14 17 9.59 0.875 50.4 42 29 14 17 1.465 45 31 14 1.493 0.938 45 31 40 8.34 0.865 48.3 42 25 12 15 8.96 0.862 54.8 42 21 12 15 1.462 45 27 10 1.496 0.936 45 27 14 8.45 0.861 46.6 42 27 16 17 8.78 0.860 55.5 42 19 40 15 1.460 45 29 12 1.513 0.925 45 29 12 8.53 0.858 45.4 42 21 16 17 9.19 0.859 53.0 42 27 12 15 1.450 43 29 16 1.553 0.901 45 9 26 8.29 0.852 47.4 42 33 14 17 9.28 0.851 51.0 42 27 16 17 1.420 45 33 42 1.555 0.901 43 29 38 8.03 0.848 49.9 42 21 12 15 9.37 0.850 49.8 42 21 16 17 1.409 45 9 28 1.560 0.897 45 19 12 8.27 0.836 45.9 42 23 18 17 8.75 0.850 55.2 41 37 40 15 1.406 44 17 40 1.564 0.895 45 31 44 8.32 0.829 44.5 42 17 16 17 8.69 0.842 55.1 41 13 16 15 1.402 43 19 38 1.572 0.890 44 17 14 7.95 0.825 48.3 41 15 40 15 8.40 0.834 56.1 42 33 10 15 1.400 45 31 44 1.582 0.885 44 13 36 7.80 0.820 49.6 41 13 16 15 9.10 0.828 50.2 42 23 18 17
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.49 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 17,501.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-53 Cycle: 23 Core Average Exposure: MWd/MTU 34458.3 Exposure: MWd/MTU (GWd) 17800.0 (1807.50 )
| |
| Delta E: MWd/MTU, (GWd) 299.0 ( 30.36 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.8 Top 25 0.266 6.884 37 0.685 0.710 3 24 Inlet Subcooling: Btu/lbm -20.29 24 0.595 17.339 38 0.370 0.583 37 48 Flow: Mlb/hr 80.46 (104.50 %) 23 0.985 24.728 39 0.399 0.771 17 48 22 1.157 29.114 40 0.455 0.901 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.238 31.574 41 0.837 1.198 9 30 51 -- -- -- -- -- 51 20 1.305 33.366 42 1.087 1.246 31 16 47 -- -- -- -- -- -- -- -- -- 47 19 1.337 34.365 43 1.248 1.440 29 38 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.362* 35.572 44 1.263 1.409 17 40 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.362 36.512 45 1.343 1.471 27 40 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.343 37.093 31 -- -- -- -- 6 -- -- -- 6 -- -- -- -- 31 15 1.345 37.635 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.306 38.100 23 -- -- -- -- 6 -- -- -- 6 -- -- -- -- 23 13 1.337 38.067 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.301 39.470 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.233 40.393 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.191 40.146 7 -- -- -- -- -- -- -- -- -- 7 9 1.126 40.937 3 -- -- -- -- -- 3 8 1.036 41.548 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.938 42.164 6 0.836 43.057 5 0.723 43.191*
| |
| 4 0.615 42.038 Control Rod Density: % 2.55 3 0.527 39.415 2 0.415 31.021 k-effective: 1.00038 Bottom 1 0.120 9.126 Void Fraction: 0.381 Core Delta-P: psia 23.532 % AXIAL TILT 14.959 -11.262 Core Plate Delta-P: psia 18.999 AVG BOT 8ft/12ft 0.9335 1.0649 Coolant Temp: Deg-F 547.3 In Channel Flow: Mlb/hr 71.00 Active Channel Flow: Mlb/hr 68.71 Total Bypass Flow (%): 11.8 (of total core flow)
| |
| Total Water Rod Flow (%): 2.8 (of total core flow)
| |
| Source Convergence 0.00037 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.471 45 27 40 1.513 0.925 45 27 44 8.76 0.887 46.0 42 29 14 17 9.66 0.886 51.0 42 29 14 17 1.463 45 27 44 1.544 0.907 45 31 40 8.69 0.880 46.1 42 25 12 17 9.02 0.880 55.4 42 21 12 15 1.459 45 31 40 1.551 0.902 45 25 40 8.49 0.870 47.1 42 27 16 17 8.85 0.879 56.1 42 19 40 15 1.458 45 29 42 1.566 0.894 45 29 12 8.59 0.869 46.0 42 21 16 17 8.86 0.872 55.7 41 37 40 15 1.440 43 29 38 1.584 0.884 45 9 26 8.42 0.866 47.5 42 19 14 17 9.56 0.872 50.4 42 27 12 17 1.422 45 33 42 1.605 0.872 45 19 12 8.41 0.864 47.4 42 21 12 17 8.83 0.867 55.6 41 13 16 15 1.422 45 9 28 1.607 0.871 45 21 44 8.30 0.843 46.4 42 23 18 17 9.37 0.862 51.4 42 27 38 17 1.409 44 17 40 1.610 0.870 43 29 38 8.42 0.843 45.0 42 17 16 17 9.44 0.862 50.4 42 21 16 17 1.405 45 31 44 1.620 0.864 44 17 40 8.24 0.841 46.8 41 37 40 17 8.48 0.853 56.6 42 33 10 15 1.404 45 11 30 1.621 0.864 44 13 36 8.18 0.837 47.0 41 13 16 17 9.26 0.837 49.3 42 29 44 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.50 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 17,800.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-54 Cycle: 23 Core Average Exposure: MWd/MTU 34459.2 Exposure: MWd/MTU (GWd) 17801.0 (1807.60 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.247 6.884 37 0.671 0.702 3 24 Inlet Subcooling: Btu/lbm -22.59 24 0.550 17.339 38 0.363 0.577 5 16 Flow: Mlb/hr 73.15 ( 95.00 %) 23 0.912 24.729 39 0.389 0.749 17 48 22 1.084 29.115 40 0.446 0.877 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.185 31.575 41 0.821 1.197 9 24 51 -- -- -- -- -- 51 20 1.268 33.367 42 1.101 1.235 15 18 47 -- -- -- -- -- -- -- -- -- 47 19 1.313 34.366 43 1.301 1.443 29 38 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.348 35.574 44 1.238 1.424 13 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.357* 36.513 45 1.323 1.454 31 40 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.345 37.094 31 -- -- -- -- 0 -- -- -- -- -- -- -- -- 31 15 1.350 37.637 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.314 38.101 23 -- -- -- -- -- -- -- -- 0 -- -- -- -- 23 13 1.345 38.069 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.309 39.471 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.242 40.394 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.202 40.147 7 -- -- -- -- -- -- -- -- -- 7 9 1.138 40.938 3 -- -- -- -- -- 3 8 1.055 41.549 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.965 42.165 6 0.872 43.058 5 0.768 43.192*
| |
| 4 0.664 42.039 Control Rod Density: % 1.46 3 0.576 39.416 2 0.458 31.021 k-effective: 1.00038 Bottom 1 0.133 9.126 Void Fraction: 0.400 Core Delta-P: psia 20.602 % AXIAL TILT 12.221 -11.261 Core Plate Delta-P: psia 16.076 AVG BOT 8ft/12ft 0.9536 1.0649 Coolant Temp: Deg-F 547.1 In Channel Flow: Mlb/hr 64.37 Active Channel Flow: Mlb/hr 62.23 Total Bypass Flow (%): 12.0 (of total core flow)
| |
| Total Water Rod Flow (%): 2.9 (of total core flow)
| |
| Source Convergence 0.00047 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.454 45 31 40 1.495 0.936 45 13 22 8.63 0.873 46.0 42 21 16 17 8.84 0.868 55.6 41 13 16 15 1.451 45 13 22 1.496 0.936 45 31 40 8.59 0.871 46.2 42 19 18 17 9.04 0.868 54.7 42 19 14 15 1.450 45 27 40 1.501 0.932 45 27 44 8.57 0.868 46.1 42 17 20 17 8.81 0.867 55.8 41 37 40 15 1.443 43 29 38 1.524 0.918 45 27 40 8.52 0.867 46.6 42 23 14 17 8.87 0.865 55.4 42 21 12 15 1.438 43 21 18 1.534 0.913 45 9 26 8.56 0.862 45.5 42 15 22 17 9.47 0.864 50.4 42 21 16 17 1.437 43 17 18 1.542 0.908 45 13 26 8.37 0.861 47.5 42 19 14 17 9.42 0.861 50.6 42 19 18 17 1.434 45 29 42 1.548 0.904 44 13 18 8.20 0.857 49.0 42 13 20 15 9.15 0.860 53.6 42 13 20 15 1.431 43 15 20 1.556 0.900 45 29 42 8.37 0.856 47.1 42 25 16 17 9.36 0.860 51.1 42 23 14 17 1.428 45 27 44 1.559 0.898 45 11 20 8.23 0.855 48.5 42 27 42 15 9.40 0.859 50.5 42 17 20 17 1.428 45 13 26 1.560 0.898 43 29 38 8.54 0.855 45.0 42 17 16 17 9.17 0.854 52.6 42 15 22 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.51 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 17,801.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-55 Cycle: 23 Core Average Exposure: MWd/MTU 34808.2 Exposure: MWd/MTU (GWd) 18150.0 (1843.04 )
| |
| Delta E: MWd/MTU, (GWd) 349.0 ( 35.44 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.8 Top 25 0.254 6.978 37 0.673 0.704 3 24 Inlet Subcooling: Btu/lbm -20.29 24 0.569 17.549 38 0.361 0.577 5 16 Flow: Mlb/hr 80.46 (104.50 %) 23 0.946 25.081 39 0.389 0.751 17 48 22 1.123 29.533 40 0.445 0.883 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.227 32.033 41 0.823 1.206 9 24 51 -- -- -- -- -- 51 20 1.309 33.857 42 1.097 1.233 15 18 47 -- -- -- -- -- -- -- -- -- 47 19 1.348 34.872 43 1.291 1.434 29 38 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.378 36.092 44 1.246 1.425 13 18 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.379* 37.033 45 1.329 1.451 13 22 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.361 37.603 31 -- -- -- -- 0 -- -- -- -- -- -- -- -- 31 15 1.362 38.134 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.320 38.585 23 -- -- -- -- -- -- -- -- 0 -- -- -- -- 23 13 1.348 38.522 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.308 39.912 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.236 40.811 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.193 40.534 7 -- -- -- -- -- -- -- -- -- 7 9 1.125 41.302 3 -- -- -- -- -- 3 8 1.034 41.885 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.936 42.470 6 0.834 43.333 5 0.723 43.431*
| |
| 4 0.616 42.244 Control Rod Density: % 1.46 3 0.530 39.594 2 0.420 31.162 k-effective: 1.00036 Bottom 1 0.122 9.170 Void Fraction: 0.381 Core Delta-P: psia 23.560 % AXIAL TILT 14.802 -10.938 Core Plate Delta-P: psia 19.030 AVG BOT 8ft/12ft 0.9375 1.0633 Coolant Temp: Deg-F 547.3 In Channel Flow: Mlb/hr 70.98 Active Channel Flow: Mlb/hr 68.70 Total Bypass Flow (%): 11.8 (of total core flow)
| |
| Total Water Rod Flow (%): 2.8 (of total core flow)
| |
| Source Convergence 0.00029 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.451 45 13 22 1.548 0.904 45 27 44 8.69 0.885 46.6 42 21 16 17 8.97 0.896 56.3 41 13 16 15 1.451 45 31 40 1.553 0.901 45 13 22 8.60 0.882 47.2 42 23 14 17 8.91 0.892 56.4 41 37 40 15 1.447 45 27 40 1.558 0.899 45 31 40 8.64 0.882 46.8 42 19 18 17 8.93 0.886 56.0 42 21 12 15 1.437 45 27 44 1.576 0.888 45 9 26 8.63 0.879 46.7 42 17 20 17 9.07 0.886 55.4 42 19 14 15 1.436 45 29 42 1.589 0.881 45 27 40 8.46 0.878 48.4 42 33 40 17 9.54 0.875 51.0 42 21 16 17 1.434 43 29 38 1.596 0.877 45 13 28 8.64 0.876 46.1 42 15 22 17 9.22 0.875 54.2 42 13 20 15 1.431 45 11 24 1.608 0.871 44 13 18 8.54 0.874 47.0 42 13 20 17 8.93 0.874 55.5 42 11 22 15 1.430 45 13 26 1.610 0.870 45 11 20 8.56 0.873 46.7 42 25 12 17 9.45 0.874 51.8 42 23 14 17 1.430 43 17 18 1.615 0.867 45 29 42 8.63 0.870 45.6 42 17 16 17 9.48 0.872 51.3 42 19 18 17 1.427 45 9 26 1.619 0.865 45 11 24 8.43 0.869 47.7 42 27 38 17 9.47 0.870 51.2 42 17 20 17
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.52 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 18,150.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-56 Cycle: 23 Core Average Exposure: MWd/MTU 34809.2 Exposure: MWd/MTU (GWd) 18151.0 (1843.14 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.259 6.978 37 0.664 0.688 3 24 Inlet Subcooling: Btu/lbm -22.33 24 0.576 17.550 38 0.356 0.568 47 16 Flow: Mlb/hr 73.92 ( 96.00 %) 23 0.954 25.082 39 0.383 0.734 17 48 22 1.129 29.535 40 0.438 0.863 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.228 32.035 41 0.810 1.188 43 30 51 -- -- -- -- -- 51 20 1.306 33.858 42 1.111 1.239 31 16 47 -- -- -- -- -- -- -- -- -- 47 19 1.343 34.873 43 1.332 1.433 37 24 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.371 36.093 44 1.225 1.396 39 36 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.371* 37.035 45 1.312 1.462 39 26 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.352 37.605 31 -- -- -- -- 6 -- -- -- -- -- -- -- -- 31 15 1.352 38.136 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.310 38.586 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.335 38.523 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.294 39.913 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.223 40.812 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.181 40.535 7 -- -- -- -- -- -- -- -- -- 7 9 1.116 41.303 3 -- -- -- -- -- 3 8 1.031 41.886 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.938 42.471 6 0.843 43.333 5 0.738 43.432*
| |
| 4 0.635 42.245 Control Rod Density: % 0.64 3 0.550 39.594 2 0.438 31.163 k-effective: 1.00057 Bottom 1 0.128 9.171 Void Fraction: 0.393 Core Delta-P: psia 20.848 % AXIAL TILT 14.511 -10.937 Core Plate Delta-P: psia 16.325 AVG BOT 8ft/12ft 0.9376 1.0633 Coolant Temp: Deg-F 547.1 In Channel Flow: Mlb/hr 65.09 Active Channel Flow: Mlb/hr 62.95 Total Bypass Flow (%): 11.9 (of total core flow)
| |
| Total Water Rod Flow (%): 2.9 (of total core flow)
| |
| Source Convergence 0.00047 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.462 45 39 26 1.502 0.932 45 39 28 8.55 0.871 46.6 42 29 14 17 9.44 0.871 51.6 42 29 14 17 1.444 45 39 22 1.527 0.917 45 39 32 8.55 0.870 46.5 42 39 24 17 8.66 0.867 56.4 41 37 40 15 1.433 43 37 24 1.534 0.913 45 43 28 8.55 0.868 46.4 42 37 32 17 8.67 0.866 56.3 41 13 16 15 1.428 45 27 14 1.543 0.907 45 31 14 8.52 0.867 46.6 42 21 16 17 9.09 0.865 54.3 42 39 24 15 1.427 45 31 14 1.546 0.905 45 27 14 8.47 0.865 46.9 42 35 34 17 8.70 0.863 56.0 42 21 12 15 1.425 45 41 24 1.548 0.904 45 27 44 8.41 0.865 47.4 42 33 18 17 9.43 0.862 50.5 42 37 22 17 1.421 43 29 16 1.570 0.892 45 29 12 8.52 0.863 46.0 42 37 28 17 8.83 0.862 55.4 42 19 14 15 1.421 43 31 18 1.573 0.890 43 37 30 8.35 0.862 47.8 42 27 16 17 9.35 0.858 51.1 42 21 16 17 1.418 45 43 26 1.578 0.887 45 41 24 8.38 0.857 47.0 42 39 34 17 9.38 0.855 50.3 42 37 28 17 1.416 43 35 22 1.588 0.882 43 35 22 8.24 0.857 48.6 42 33 14 17 9.28 0.854 51.3 42 35 34 17
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.53 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 18,151.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-57 Cycle: 23 Core Average Exposure: MWd/MTU 35158.3 Exposure: MWd/MTU (GWd) 18500.0 (1878.58 )
| |
| Delta E: MWd/MTU, (GWd) 349.0 ( 35.44 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.8 Top 25 0.266 7.076 37 0.666 0.691 3 24 Inlet Subcooling: Btu/lbm -20.29 24 0.594 17.770 38 0.356 0.565 47 16 Flow: Mlb/hr 80.46 (104.50 %) 23 0.986 25.449 39 0.383 0.737 17 48 22 1.165 29.969 40 0.438 0.870 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.266 32.509 41 0.812 1.191 43 30 51 -- -- -- -- -- 51 20 1.342 34.361 42 1.107 1.230 31 16 47 -- -- -- -- -- -- -- -- -- 47 19 1.373 35.389 43 1.321 1.421 37 24 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.395* 36.619 44 1.232 1.395 39 36 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.389 37.559 45 1.318 1.456 39 26 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.363 38.116 31 -- -- -- -- 6 -- -- -- -- -- -- -- -- 31 15 1.359 38.633 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.312 39.067 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.335 38.973 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.291 40.348 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.217 41.223 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.173 40.915 7 -- -- -- -- -- -- -- -- -- 7 9 1.105 41.660 3 -- -- -- -- -- 3 8 1.012 42.215 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.912 42.769 6 0.810 43.600 5 0.700 43.664*
| |
| 4 0.596 42.443 Control Rod Density: % 0.64 3 0.513 39.765 2 0.407 31.299 k-effective: 1.00012 Bottom 1 0.119 9.213 Void Fraction: 0.376 Core Delta-P: psia 23.497 % AXIAL TILT 16.719 -10.600 Core Plate Delta-P: psia 18.972 AVG BOT 8ft/12ft 0.9232 1.0616 Coolant Temp: Deg-F 547.2 In Channel Flow: Mlb/hr 71.01 Active Channel Flow: Mlb/hr 68.73 Total Bypass Flow (%): 11.7 (of total core flow)
| |
| Total Water Rod Flow (%): 2.8 (of total core flow)
| |
| Source Convergence 0.00043 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.456 45 39 26 1.564 0.895 45 39 28 8.60 0.882 47.2 42 29 14 17 8.78 0.891 56.9 41 13 16 15 1.437 45 39 22 1.583 0.884 45 43 28 8.60 0.881 47.1 42 39 24 17 8.74 0.889 57.0 41 37 40 15 1.422 45 27 14 1.586 0.882 45 39 32 8.56 0.877 47.2 42 21 16 17 9.05 0.882 55.4 42 29 14 15 1.422 45 41 24 1.588 0.882 45 27 44 8.58 0.877 47.0 42 37 32 17 8.74 0.881 56.7 42 21 12 15 1.421 45 31 14 1.597 0.877 45 21 14 8.49 0.873 47.5 42 35 34 17 8.85 0.878 56.0 42 19 14 15 1.421 43 37 24 1.607 0.871 45 27 14 8.48 0.873 47.6 42 33 36 17 9.07 0.877 55.0 42 39 24 15 1.421 45 43 28 1.625 0.862 45 29 12 8.49 0.871 47.4 42 25 12 17 8.73 0.869 56.2 42 11 22 15 1.411 43 29 16 1.636 0.856 45 41 30 8.46 0.871 47.6 42 39 34 17 9.44 0.868 51.2 42 37 22 17 1.409 45 27 10 1.636 0.856 43 37 30 8.33 0.870 49.0 42 33 40 17 9.39 0.867 51.7 42 21 16 17 1.407 43 31 18 1.640 0.854 45 11 20 8.49 0.870 47.2 42 41 26 17 8.99 0.867 54.9 42 13 20 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.54 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 18,500.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-58 Cycle: 23 Core Average Exposure: MWd/MTU 35159.3 Exposure: MWd/MTU (GWd) 18501.0 (1878.68 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.8 Top 25 0.261 7.077 37 0.659 0.689 3 24 Inlet Subcooling: Btu/lbm -21.56 24 0.580 17.770 38 0.351 0.559 5 16 Flow: Mlb/hr 76.23 ( 99.00 %) 23 0.963 25.450 39 0.380 0.734 17 48 22 1.141 29.970 40 0.434 0.877 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.247 32.510 41 0.802 1.190 9 30 51 -- -- -- -- -- 51 20 1.327 34.363 42 1.116 1.219 15 28 47 -- -- -- -- -- -- -- -- -- 47 19 1.362 35.391 43 1.352 1.435 15 30 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.387* 36.621 44 1.217 1.397 13 36 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.383 37.561 45 1.306 1.460 13 28 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.361 38.118 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.357 38.635 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.312 39.069 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.334 38.974 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.290 40.350 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.217 41.224 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.174 40.916 7 -- -- -- -- -- -- -- -- -- 7 9 1.107 41.661 3 -- -- -- -- -- 3 8 1.019 42.216 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.924 42.770 6 0.827 43.600 5 0.721 43.664*
| |
| 4 0.619 42.444 Control Rod Density: % 0.00 3 0.536 39.766 2 0.427 31.299 k-effective: 1.00029 Bottom 1 0.125 9.213 Void Fraction: 0.386 Core Delta-P: psia 21.764 % AXIAL TILT 15.622 -10.599 Core Plate Delta-P: psia 17.242 AVG BOT 8ft/12ft 0.9306 1.0616 Coolant Temp: Deg-F 547.1 In Channel Flow: Mlb/hr 67.18 Active Channel Flow: Mlb/hr 64.99 Total Bypass Flow (%): 11.9 (of total core flow)
| |
| Total Water Rod Flow (%): 2.9 (of total core flow)
| |
| Source Convergence 0.00034 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.460 45 13 28 1.516 0.924 45 13 28 8.64 0.881 46.8 42 15 32 17 8.62 0.884 57.3 42 19 40 15 1.444 45 13 32 1.537 0.911 45 13 32 8.59 0.879 47.0 42 13 30 17 9.52 0.878 51.6 42 13 30 17 1.435 43 15 30 1.549 0.904 45 9 26 8.67 0.875 45.8 42 15 28 17 8.64 0.877 56.9 41 13 16 15 1.424 45 11 30 1.567 0.893 45 11 30 8.51 0.873 47.3 42 17 34 17 8.69 0.877 56.7 41 15 40 15 1.418 45 9 28 1.583 0.885 45 27 44 8.46 0.870 47.6 42 13 34 17 9.49 0.872 51.1 42 15 32 17 1.415 43 17 32 1.583 0.884 45 21 40 8.44 0.868 47.5 42 19 36 17 8.75 0.871 56.2 42 11 22 15 1.409 43 15 34 1.599 0.876 44 13 36 8.43 0.867 47.5 42 21 38 17 9.11 0.869 54.5 42 11 28 15 1.408 45 25 40 1.601 0.875 43 15 30 8.51 0.867 46.6 42 17 30 17 9.03 0.866 54.7 42 13 34 15 1.406 45 21 40 1.606 0.872 45 25 40 8.51 0.867 46.6 42 11 28 17 9.50 0.866 50.2 42 15 28 17 1.406 43 19 34 1.620 0.864 45 11 34 8.36 0.863 47.8 42 23 40 17 8.57 0.864 56.7 42 21 42 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.55 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 18,501.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-59 Cycle: 23 Core Average Exposure: MWd/MTU 35397.5 Exposure: MWd/MTU (GWd) 18739.2 (1902.87 )
| |
| Delta E: MWd/MTU, (GWd) 238.2 ( 24.19 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.8 Top 25 0.265 7.144 37 0.660 0.691 3 24 Inlet Subcooling: Btu/lbm -20.29 24 0.593 17.921 38 0.351 0.560 5 16 Flow: Mlb/hr 80.46 (104.50 %) 23 0.984 25.702 39 0.380 0.735 17 48 22 1.165 30.269 40 0.434 0.879 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.272 32.837 41 0.804 1.194 9 30 51 -- -- -- -- -- 51 20 1.350 34.710 42 1.114 1.215 15 28 47 -- -- -- -- -- -- -- -- -- 47 19 1.381 35.746 43 1.345 1.430 15 30 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.401* 36.982 44 1.221 1.398 13 36 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.393 37.921 45 1.310 1.460 13 28 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.367 38.468 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.361 38.975 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.312 39.398 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.333 39.281 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.287 40.646 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.212 41.503 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.167 41.174 7 -- -- -- -- -- -- -- -- -- 7 9 1.099 41.903 3 -- -- -- -- -- 3 8 1.007 42.438 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.907 42.971 6 0.807 43.780 5 0.698 43.820*
| |
| 4 0.596 42.577 Control Rod Density: % 0.00 3 0.514 39.881 2 0.409 31.391 k-effective: 0.99974 Bottom 1 0.120 9.242 Void Fraction: 0.375 Core Delta-P: psia 23.498 % AXIAL TILT 16.988 -10.368 Core Plate Delta-P: psia 18.975 AVG BOT 8ft/12ft 0.9215 1.0604 Coolant Temp: Deg-F 547.2 In Channel Flow: Mlb/hr 71.01 Active Channel Flow: Mlb/hr 68.73 Total Bypass Flow (%): 11.8 (of total core flow)
| |
| Total Water Rod Flow (%): 2.8 (of total core flow)
| |
| Source Convergence 0.00047 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.460 45 13 28 1.550 0.910 45 13 28 8.64 0.888 47.4 42 13 30 17 8.63 0.896 57.8 42 19 40 15 1.444 45 13 32 1.571 0.897 45 13 32 8.66 0.888 47.2 42 15 32 17 8.70 0.893 57.4 41 13 16 15 1.430 43 15 30 1.575 0.895 45 9 26 8.69 0.882 46.2 42 15 28 17 8.74 0.892 57.1 41 15 40 15 1.427 45 11 30 1.597 0.883 45 11 30 8.52 0.881 48.0 42 13 34 17 9.57 0.886 52.0 42 13 30 17 1.424 45 9 28 1.609 0.876 45 27 44 8.59 0.879 47.0 42 11 28 17 8.79 0.885 56.6 42 11 22 15 1.409 43 17 32 1.618 0.871 45 21 40 8.52 0.879 47.7 42 17 34 17 9.15 0.882 54.9 42 11 28 15 1.407 45 25 40 1.628 0.866 44 13 36 8.45 0.874 48.0 42 19 36 17 9.52 0.878 51.6 42 15 32 17 1.406 45 21 40 1.637 0.861 43 15 30 8.45 0.873 48.0 42 21 38 17 8.60 0.877 57.1 42 21 42 15 1.406 43 15 34 1.643 0.858 45 25 40 8.41 0.872 48.2 42 23 40 17 9.04 0.877 55.1 42 13 34 15 1.401 43 17 36 1.647 0.856 45 11 34 8.51 0.870 47.0 42 17 30 17 9.54 0.872 50.7 42 15 28 17
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.56 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 18,739.2 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-60 Cycle: 23 Core Average Exposure: MWd/MTU 35398.5 Exposure: MWd/MTU (GWd) 18740.2 (1902.97 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.262 7.144 37 0.665 0.696 3 24 Inlet Subcooling: Btu/lbm -25.15 24 0.586 17.921 38 0.352 0.564 5 16 Flow: Mlb/hr 76.23 ( 99.00 %) 23 0.970 25.703 39 0.381 0.740 17 48 22 1.144 30.270 40 0.436 0.883 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.246 32.838 41 0.808 1.193 9 30 51 -- -- -- -- -- 51 20 1.321 34.711 42 1.113 1.213 15 28 47 -- -- -- -- -- -- -- -- -- 47 19 1.352 35.748 43 1.342 1.428 15 30 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.373* 36.984 44 1.222 1.396 13 36 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.366 37.922 45 1.308 1.458 13 28 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.343 38.470 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.341 38.977 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.297 39.399 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.325 39.282 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.286 40.647 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.218 41.505 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.183 41.175 7 -- -- -- -- -- -- -- -- -- 7 9 1.123 41.904 3 -- -- -- -- -- 3 8 1.037 42.439 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.942 42.972 6 0.842 43.780 5 0.730 43.821*
| |
| 4 0.622 42.578 Control Rod Density: % 0.00 3 0.538 39.881 2 0.428 31.391 k-effective: 0.99995 Bottom 1 0.125 9.242 Void Fraction: 0.372 Core Delta-P: psia 21.497 % AXIAL TILT 14.897 -10.367 Core Plate Delta-P: psia 16.953 AVG BOT 8ft/12ft 0.9326 1.0604 Coolant Temp: Deg-F 546.3 In Channel Flow: Mlb/hr 67.28 Active Channel Flow: Mlb/hr 65.11 Total Bypass Flow (%): 11.7 (of total core flow)
| |
| Total Water Rod Flow (%): 2.8 (of total core flow)
| |
| Source Convergence 0.00045 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.458 45 13 28 1.538 0.917 45 13 28 8.44 0.868 47.4 42 13 30 17 8.49 0.881 57.8 42 19 40 15 1.441 45 13 32 1.562 0.903 45 13 32 8.47 0.868 47.2 42 15 32 17 8.56 0.879 57.4 41 13 16 15 1.428 43 15 30 1.567 0.900 45 9 26 8.50 0.862 46.2 42 15 28 17 8.60 0.877 57.1 41 15 40 15 1.424 45 11 30 1.581 0.892 45 11 30 8.33 0.861 48.0 42 13 34 17 8.64 0.869 56.6 42 11 22 15 1.422 45 9 28 1.602 0.880 45 27 44 8.40 0.859 47.0 42 11 28 17 9.35 0.866 52.0 42 13 30 17 1.406 43 17 32 1.612 0.875 45 21 40 8.33 0.859 47.7 42 17 34 17 8.98 0.866 54.9 42 11 28 15 1.404 45 25 40 1.615 0.873 44 13 36 8.27 0.854 48.0 42 19 36 17 8.46 0.863 57.1 42 21 42 15 1.403 45 21 40 1.620 0.870 43 15 30 8.27 0.854 48.0 42 21 38 17 8.88 0.861 55.1 42 13 34 15 1.403 43 15 34 1.630 0.865 45 25 40 8.23 0.852 48.2 42 23 40 17 9.30 0.858 51.6 42 15 32 17 1.398 43 17 36 1.631 0.865 45 11 34 8.32 0.851 47.0 42 17 30 17 8.71 0.856 55.6 42 23 40 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.57 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 18,740.2 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-61 Cycle: 23 Core Average Exposure: MWd/MTU 35608.3 Exposure: MWd/MTU (GWd) 18950.0 (1924.27 )
| |
| Delta E: MWd/MTU, (GWd) 209.8 ( 21.30 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.266 7.203 37 0.666 0.696 3 24 Inlet Subcooling: Btu/lbm -23.68 24 0.599 18.055 38 0.352 0.563 5 16 Flow: Mlb/hr 80.46 (104.50 %) 23 0.992 25.926 39 0.380 0.741 17 48 22 1.168 30.533 40 0.435 0.885 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.270 33.125 41 0.809 1.197 9 30 51 -- -- -- -- -- 51 20 1.344 35.016 42 1.111 1.211 15 28 47 -- -- -- -- -- -- -- -- -- 47 19 1.371 36.059 43 1.337 1.424 15 30 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.388* 37.299 44 1.226 1.397 13 36 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.378 38.236 45 1.312 1.458 13 28 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.351 38.775 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.347 39.273 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.301 39.686 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.327 39.551 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.287 40.908 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.216 41.751 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.179 41.405 7 -- -- -- -- -- -- -- -- -- 7 9 1.116 42.121 3 -- -- -- -- -- 3 8 1.025 42.639 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.924 43.152 6 0.818 43.941 5 0.703 43.959*
| |
| 4 0.595 42.695 Control Rod Density: % 0.00 3 0.511 39.983 2 0.407 31.472 k-effective: 0.99973 Bottom 1 0.119 9.268 Void Fraction: 0.361 Core Delta-P: psia 23.211 % AXIAL TILT 16.377 -10.170 Core Plate Delta-P: psia 18.666 AVG BOT 8ft/12ft 0.9233 1.0594 Coolant Temp: Deg-F 546.4 In Channel Flow: Mlb/hr 71.11 Active Channel Flow: Mlb/hr 68.86 Total Bypass Flow (%): 11.6 (of total core flow)
| |
| Total Water Rod Flow (%): 2.8 (of total core flow)
| |
| Source Convergence 0.00038 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.458 45 13 28 1.570 0.898 45 13 28 8.51 0.879 47.8 42 13 30 17 8.63 0.895 57.7 41 13 16 15 1.441 45 13 32 1.592 0.885 45 9 26 8.52 0.876 47.6 42 15 32 17 8.67 0.893 57.5 41 15 40 15 1.428 45 9 28 1.595 0.884 45 13 32 8.40 0.872 48.4 42 13 34 17 8.52 0.893 58.2 42 19 40 15 1.427 45 11 30 1.610 0.876 45 11 30 8.49 0.872 47.4 42 11 28 17 8.69 0.884 57.0 42 11 22 15 1.424 43 15 30 1.627 0.866 45 27 44 8.54 0.870 46.6 42 15 28 17 9.04 0.880 55.3 42 11 28 15 1.404 45 25 40 1.643 0.858 44 13 36 8.37 0.866 48.1 42 17 34 17 9.13 0.878 54.8 42 13 30 15 1.403 45 21 40 1.645 0.857 45 21 40 8.29 0.862 48.6 42 23 40 17 8.51 0.876 57.5 42 21 42 15 1.400 43 15 34 1.655 0.852 43 15 30 8.31 0.862 48.3 42 21 38 17 8.92 0.873 55.5 42 13 34 15 1.400 45 25 44 1.656 0.852 45 11 34 8.30 0.862 48.3 42 19 36 17 8.75 0.867 56.0 42 25 42 15 1.400 43 17 32 1.660 0.850 45 11 36 8.33 0.860 48.0 42 11 32 17 8.74 0.867 56.0 42 23 40 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.58 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 18,950.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-62 Cycle: 23 Core Average Exposure: MWd/MTU 35609.3 Exposure: MWd/MTU (GWd) 18951.0 (1924.38 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.261 7.204 37 0.671 0.701 3 24 Inlet Subcooling: Btu/lbm -28.45 24 0.586 18.056 38 0.353 0.567 5 16 Flow: Mlb/hr 76.23 ( 99.00 %) 23 0.969 25.928 39 0.382 0.746 17 48 22 1.142 30.534 40 0.438 0.890 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.242 33.127 41 0.813 1.194 9 30 51 -- -- -- -- -- 51 20 1.315 35.017 42 1.110 1.207 15 28 47 -- -- -- -- -- -- -- -- -- 47 19 1.343 36.060 43 1.334 1.419 15 30 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.362* 37.301 44 1.227 1.393 13 36 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.354 38.237 45 1.311 1.453 13 28 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.331 38.776 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.330 39.275 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.289 39.687 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.321 39.552 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.287 40.909 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.224 41.752 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.195 41.406 7 -- -- -- -- -- -- -- -- -- 7 9 1.140 42.122 3 -- -- -- -- -- 3 8 1.055 42.640 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.958 43.153 6 0.853 43.942 5 0.734 43.960*
| |
| 4 0.622 42.696 Control Rod Density: % 0.00 3 0.536 39.983 2 0.426 31.472 k-effective: 0.99970 Bottom 1 0.124 9.268 Void Fraction: 0.359 Core Delta-P: psia 21.260 % AXIAL TILT 14.220 -10.169 Core Plate Delta-P: psia 16.702 AVG BOT 8ft/12ft 0.9353 1.0594 Coolant Temp: Deg-F 545.5 In Channel Flow: Mlb/hr 67.36 Active Channel Flow: Mlb/hr 65.22 Total Bypass Flow (%): 11.6 (of total core flow)
| |
| Total Water Rod Flow (%): 2.8 (of total core flow)
| |
| Source Convergence 0.00047 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.453 45 13 28 1.560 0.904 45 13 28 8.33 0.860 47.8 42 13 30 17 8.51 0.883 57.8 41 13 16 15 1.436 45 13 32 1.583 0.890 45 9 26 8.34 0.858 47.6 42 15 32 17 8.55 0.880 57.5 41 15 40 15 1.424 45 9 28 1.584 0.890 45 13 32 8.23 0.854 48.4 42 13 34 17 8.40 0.880 58.2 42 19 40 15 1.422 45 11 30 1.600 0.881 45 11 30 8.31 0.854 47.4 42 11 28 17 8.56 0.870 57.0 42 11 22 15 1.419 43 15 30 1.616 0.872 45 27 44 8.36 0.851 46.6 42 15 28 17 8.89 0.866 55.3 42 11 28 15 1.399 45 25 40 1.633 0.864 44 13 36 8.20 0.848 48.1 42 17 34 17 8.39 0.864 57.5 42 21 42 15 1.399 45 21 40 1.636 0.862 45 21 40 8.12 0.845 48.6 42 23 40 17 8.98 0.863 54.8 42 13 30 15 1.397 45 25 44 1.644 0.858 43 15 30 8.14 0.844 48.3 42 21 38 17 8.78 0.860 55.5 42 13 34 15 1.396 43 15 34 1.646 0.857 45 11 34 8.13 0.844 48.3 42 19 36 17 8.61 0.854 56.0 42 25 42 15 1.395 43 17 32 1.650 0.854 45 11 36 8.16 0.843 48.0 42 11 32 17 8.61 0.853 56.0 42 23 40 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.59 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 18,951.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-63 Cycle: 23 Core Average Exposure: MWd/MTU 35808.2 Exposure: MWd/MTU (GWd) 19150.0 (1944.58 )
| |
| Delta E: MWd/MTU, (GWd) 199.0 ( 20.21 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.265 7.260 37 0.671 0.701 3 24 Inlet Subcooling: Btu/lbm -26.80 24 0.598 18.183 38 0.352 0.567 5 16 Flow: Mlb/hr 80.46 (104.50 %) 23 0.991 26.139 39 0.381 0.746 17 48 22 1.166 30.784 40 0.437 0.891 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.268 33.399 41 0.813 1.199 9 30 51 -- -- -- -- -- 51 20 1.339 35.305 42 1.108 1.209 11 28 47 -- -- -- -- -- -- -- -- -- 47 19 1.363 36.353 43 1.329 1.417 15 30 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.379* 37.598 44 1.230 1.396 13 36 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.367 38.532 45 1.314 1.454 13 28 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.340 39.063 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.338 39.554 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.294 39.957 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.325 39.806 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.290 41.156 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.224 41.987 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.193 41.626 7 -- -- -- -- -- -- -- -- -- 7 9 1.133 42.331 3 -- -- -- -- -- 3 8 1.042 42.832 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.937 43.327 6 0.825 44.096*
| |
| 5 0.703 44.092 4 0.591 42.807 Control Rod Density: % 0.00 3 0.507 40.079 2 0.403 31.548 k-effective: 0.99958 Bottom 1 0.118 9.292 Void Fraction: 0.348 Core Delta-P: psia 22.954 % AXIAL TILT 15.818 -9.988 Core Plate Delta-P: psia 18.397 AVG BOT 8ft/12ft 0.9256 1.0585 Coolant Temp: Deg-F 545.7 In Channel Flow: Mlb/hr 71.20 Active Channel Flow: Mlb/hr 68.97 Total Bypass Flow (%): 11.5 (of total core flow)
| |
| Total Water Rod Flow (%): 2.8 (of total core flow)
| |
| Source Convergence 0.00050 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.454 45 13 28 1.590 0.887 45 13 28 8.42 0.872 48.2 42 13 30 17 8.60 0.900 58.1 41 13 16 15 1.437 45 13 32 1.608 0.877 45 9 26 8.40 0.868 47.9 42 15 32 17 8.63 0.898 57.9 41 15 40 15 1.430 45 9 28 1.615 0.873 45 13 32 8.41 0.867 47.8 42 11 28 17 8.45 0.894 58.5 42 19 40 15 1.425 45 11 30 1.627 0.867 45 11 30 8.32 0.867 48.7 42 13 34 17 8.63 0.885 57.3 42 11 22 15 1.417 43 15 30 1.641 0.859 45 27 44 8.43 0.861 46.9 42 15 28 17 8.96 0.881 55.7 42 11 28 15 1.402 45 25 44 1.660 0.850 44 13 36 8.25 0.857 48.4 42 17 34 17 8.45 0.878 57.8 42 21 42 15 1.399 45 21 40 1.668 0.845 45 21 40 8.26 0.856 48.3 42 11 32 17 9.03 0.877 55.2 42 13 30 15 1.399 45 25 40 1.670 0.845 45 11 34 8.19 0.856 48.9 42 23 40 17 8.81 0.874 56.0 42 13 34 15 1.399 45 11 34 1.674 0.842 45 11 36 8.23 0.855 48.5 42 25 42 17 8.68 0.868 56.4 42 25 42 15 1.396 44 13 36 1.675 0.842 43 15 30 8.00 0.854 51.0 42 19 40 17 8.65 0.866 56.4 42 23 40 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.60 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 19,150.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-64 Cycle: 23 Core Average Exposure: MWd/MTU 35809.2 Exposure: MWd/MTU (GWd) 19151.0 (1944.68 )
| |
| Delta E: MWd/MTU, (GWd) 1.0 ( 0.10 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.259 7.260 37 0.676 0.705 3 24 Inlet Subcooling: Btu/lbm -31.50 24 0.585 18.183 38 0.354 0.571 5 16 Flow: Mlb/hr 76.23 ( 99.00 %) 23 0.968 26.140 39 0.382 0.751 17 48 22 1.139 30.785 40 0.440 0.895 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.239 33.400 41 0.817 1.196 9 30 51 -- -- -- -- -- 51 20 1.310 35.306 42 1.107 1.206 11 28 47 -- -- -- -- -- -- -- -- -- 47 19 1.335 36.355 43 1.326 1.412 15 30 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.352* 37.599 44 1.231 1.392 13 36 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.343 38.533 45 1.313 1.449 13 28 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.320 39.064 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.321 39.555 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.283 39.959 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.319 39.807 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.291 41.158 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.232 41.988 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.210 41.627 7 -- -- -- -- -- -- -- -- -- 7 9 1.158 42.332 3 -- -- -- -- -- 3 8 1.073 42.833 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.972 43.328 6 0.860 44.096*
| |
| 5 0.734 44.092 4 0.619 42.808 Control Rod Density: % 0.00 3 0.532 40.079 2 0.423 31.549 k-effective: 0.99942 Bottom 1 0.123 9.292 Void Fraction: 0.347 Core Delta-P: psia 21.045 % AXIAL TILT 13.629 -9.987 Core Plate Delta-P: psia 16.476 AVG BOT 8ft/12ft 0.9379 1.0585 Coolant Temp: Deg-F 544.7 In Channel Flow: Mlb/hr 67.44 Active Channel Flow: Mlb/hr 65.32 Total Bypass Flow (%): 11.5 (of total core flow)
| |
| Total Water Rod Flow (%): 2.8 (of total core flow)
| |
| Source Convergence 0.00048 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.449 45 13 28 1.579 0.893 45 13 28 8.24 0.853 48.2 42 13 30 17 8.47 0.887 58.1 41 13 16 15 1.433 45 13 32 1.598 0.882 45 9 26 8.23 0.850 47.9 42 15 32 17 8.51 0.885 57.9 41 15 40 15 1.426 45 9 28 1.604 0.879 45 13 32 8.23 0.849 47.8 42 11 28 17 8.33 0.881 58.5 42 19 40 15 1.420 45 11 30 1.616 0.872 45 11 30 8.15 0.849 48.7 42 13 34 17 8.50 0.872 57.3 42 11 22 15 1.412 43 15 30 1.630 0.865 45 27 44 8.25 0.843 46.9 42 15 28 17 8.81 0.867 55.7 42 11 28 15 1.399 45 25 44 1.649 0.855 44 13 36 8.08 0.839 48.4 42 17 34 17 8.33 0.866 57.8 42 21 42 15 1.395 45 21 40 1.658 0.851 45 21 14 8.09 0.839 48.3 42 11 32 17 8.88 0.862 55.2 42 13 30 15 1.395 45 11 34 1.659 0.850 45 11 34 8.02 0.838 48.9 42 23 40 17 8.67 0.860 56.0 42 13 34 15 1.395 45 25 40 1.664 0.847 43 15 30 8.05 0.837 48.5 42 25 42 17 8.54 0.854 56.4 42 25 42 15 1.392 44 13 36 1.665 0.847 45 11 36 7.84 0.837 51.0 42 19 40 17 8.52 0.853 56.4 42 23 40 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.61 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 19,151.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-65 Cycle: 23 Core Average Exposure: MWd/MTU 36002.0 Exposure: MWd/MTU (GWd) 19343.7 (1964.26 )
| |
| Delta E: MWd/MTU, (GWd) 192.7 ( 19.57 ) Axial Profile Edit Radial Power Power: MWt 2923.0 (100.00 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.264 7.314 37 0.676 0.705 3 24 Inlet Subcooling: Btu/lbm -29.69 24 0.598 18.306 38 0.353 0.570 5 16 Flow: Mlb/hr 80.46 (104.50 %) 23 0.991 26.345 39 0.382 0.751 17 48 22 1.165 31.026 40 0.438 0.896 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.265 33.663 41 0.817 1.200 9 30 51 -- -- -- -- -- 51 20 1.334 35.584 42 1.106 1.208 11 28 47 -- -- -- -- -- -- -- -- -- 47 19 1.356 36.637 43 1.322 1.411 15 30 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.370* 37.885 44 1.234 1.395 13 36 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.357 38.817 45 1.316 1.450 13 28 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.330 39.340 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.330 39.824 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.289 40.220 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.324 40.053 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.294 41.398 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.233 42.217 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.207 41.842 7 -- -- -- -- -- -- -- -- -- 7 9 1.150 42.537 3 -- -- -- -- -- 3 8 1.057 43.022 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.948 43.498 6 0.830 44.247*
| |
| 5 0.701 44.220 4 0.587 42.915 Control Rod Density: % 0.00 3 0.503 40.171 2 0.400 31.622 k-effective: 0.99926 Bottom 1 0.117 9.315 Void Fraction: 0.337 Core Delta-P: psia 22.727 % AXIAL TILT 15.301 -9.816 Core Plate Delta-P: psia 18.158 AVG BOT 8ft/12ft 0.9278 1.0576 Coolant Temp: Deg-F 544.9 In Channel Flow: Mlb/hr 71.28 Active Channel Flow: Mlb/hr 69.08 Total Bypass Flow (%): 11.4 (of total core flow)
| |
| Total Water Rod Flow (%): 2.7 (of total core flow)
| |
| Source Convergence 0.00046 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.450 45 13 28 1.608 0.877 45 13 28 8.33 0.866 48.5 42 13 30 17 8.57 0.905 58.5 41 13 16 15 1.434 45 13 32 1.623 0.869 45 9 26 8.34 0.863 48.1 42 11 28 17 8.60 0.902 58.2 41 15 40 15 1.432 45 9 28 1.634 0.863 45 13 32 8.24 0.862 49.1 42 13 34 17 8.37 0.896 58.9 42 19 40 15 1.423 45 11 30 1.643 0.858 45 11 30 8.30 0.861 48.3 42 15 32 17 8.57 0.887 57.7 42 11 22 15 1.411 43 15 30 1.655 0.852 45 27 44 8.32 0.853 47.3 42 15 28 17 8.89 0.882 56.1 42 11 28 15 1.403 45 25 44 1.675 0.842 44 13 36 8.19 0.853 48.6 42 11 32 17 8.40 0.881 58.2 42 21 42 15 1.399 45 11 34 1.683 0.838 45 11 34 8.15 0.850 48.9 42 25 42 17 8.95 0.876 55.5 42 13 30 15 1.396 45 21 40 1.688 0.835 45 11 36 7.92 0.850 51.4 42 19 40 17 8.74 0.875 56.4 42 13 34 15 1.395 45 25 40 1.688 0.835 45 21 14 8.11 0.850 49.3 42 23 40 17 8.61 0.869 56.7 42 25 42 15 1.395 44 13 36 1.690 0.834 45 9 32 8.15 0.849 48.8 42 17 34 17 8.37 0.866 57.7 42 9 34 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.62 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 19,343.7 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-66 Cycle: 23 Core Average Exposure: MWd/MTU 36404.9 Exposure: MWd/MTU (GWd) 19746.7 (2005.18 )
| |
| Delta E: MWd/MTU, (GWd) 403.0 ( 40.92 ) Axial Profile Edit Radial Power Power: MWt 2649.7 ( 90.65 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.274 7.430 37 0.674 0.704 3 24 Inlet Subcooling: Btu/lbm -26.71 24 0.626 18.572 38 0.351 0.568 5 16 Flow: Mlb/hr 80.46 (104.50 %) 23 1.039 26.789 39 0.380 0.750 17 48 22 1.218 31.547 40 0.436 0.899 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.319 34.229 41 0.818 1.210 9 30 51 -- -- -- -- -- 51 20 1.384 36.180 42 1.103 1.214 11 28 47 -- -- -- -- -- -- -- -- -- 47 19 1.397 37.241 43 1.315 1.410 15 30 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.402* 38.493 44 1.242 1.401 13 36 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.381 39.418 45 1.323 1.455 13 28 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.346 39.922 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.341 40.390 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.296 40.767 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.327 40.569 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.293 41.901 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.226 42.695 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.194 42.290 7 -- -- -- -- -- -- -- -- -- 7 9 1.126 42.959 3 -- -- -- -- -- 3 8 1.021 43.408 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.901 43.842 6 0.775 44.545*
| |
| 5 0.646 44.470 4 0.537 43.124 Control Rod Density: % 0.00 3 0.459 40.350 2 0.365 31.764 k-effective: 0.99964 Bottom 1 0.107 9.359 Void Fraction: 0.315 Core Delta-P: psia 22.223 % AXIAL TILT 18.473 -9.438 Core Plate Delta-P: psia 17.667 AVG BOT 8ft/12ft 0.9076 1.0557 Coolant Temp: Deg-F 545.2 In Channel Flow: Mlb/hr 71.52 Active Channel Flow: Mlb/hr 69.39 Total Bypass Flow (%): 11.1 (of total core flow)
| |
| Total Water Rod Flow (%): 2.6 (of total core flow)
| |
| Source Convergence 0.00043 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.455 45 13 28 1.751 0.805 45 13 28 7.74 0.807 48.8 42 11 28 17 7.90 0.851 59.2 41 13 16 15 1.445 45 9 28 1.769 0.797 45 9 26 7.70 0.806 49.2 42 13 30 17 7.93 0.849 58.9 41 15 40 15 1.438 45 13 32 1.785 0.790 45 13 32 7.63 0.804 49.8 42 13 34 17 7.67 0.838 59.7 42 19 40 15 1.431 45 11 30 1.788 0.789 45 11 30 7.65 0.799 49.0 42 15 32 17 7.87 0.831 58.4 42 11 22 15 1.414 45 25 44 1.798 0.784 45 27 44 7.60 0.797 49.3 42 11 32 17 8.18 0.827 56.8 42 11 28 15 1.410 43 15 30 1.821 0.774 44 13 36 7.55 0.794 49.6 42 25 42 17 7.71 0.825 58.9 42 21 42 15 1.409 45 11 34 1.823 0.773 45 11 34 7.44 0.793 50.8 42 19 40 18 8.03 0.819 57.1 42 13 34 15 1.401 44 13 36 1.829 0.771 45 11 36 7.74 0.792 47.0 42 15 28 18 8.20 0.818 56.3 42 13 30 15 1.398 45 21 40 1.835 0.768 45 9 32 7.57 0.790 48.8 42 23 40 18 8.32 0.816 55.6 41 9 30 15 1.396 45 25 40 1.847 0.763 45 21 14 7.58 0.788 48.6 42 17 34 18 7.72 0.815 58.4 42 9 34 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.63 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 19,746.7 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-67 Cycle: 23 Core Average Exposure: MWd/MTU 36858.2 Exposure: MWd/MTU (GWd) 20200.0 (2051.21 )
| |
| Delta E: MWd/MTU, (GWd) 453.3 ( 46.03 ) Axial Profile Edit Radial Power Power: MWt 2389.7 ( 81.76 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.286 7.566 37 0.674 0.704 3 24 Inlet Subcooling: Btu/lbm -23.87 24 0.657 18.885 38 0.349 0.566 5 16 Flow: Mlb/hr 80.46 (104.50 %) 23 1.094 27.314 39 0.379 0.750 17 48 22 1.279 32.162 40 0.434 0.902 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.378 34.895 41 0.819 1.219 9 30 51 -- -- -- -- -- 51 20 1.437 36.876 42 1.100 1.220 11 28 47 -- -- -- -- -- -- -- -- -- 47 19 1.439* 37.941 43 1.306 1.407 15 30 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.435 39.193 44 1.249 1.408 13 36 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.404 40.105 45 1.330 1.459 9 28 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.360 40.584 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.350 41.032 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.299 41.386 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.326 41.149 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.288 42.465 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.214 43.229 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.173 42.787 7 -- -- -- -- -- -- -- -- -- 7 9 1.095 43.424 3 -- -- -- -- -- 3 8 0.979 43.826 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.850 44.208 6 0.720 44.857*
| |
| 5 0.595 44.730 4 0.492 43.339 Control Rod Density: % 0.00 3 0.419 40.534 2 0.333 31.909 k-effective: 0.99955 Bottom 1 0.098 9.405 Void Fraction: 0.293 Core Delta-P: psia 21.753 % AXIAL TILT 21.803 -8.983 Core Plate Delta-P: psia 17.209 AVG BOT 8ft/12ft 0.8856 1.0533 Coolant Temp: Deg-F 545.5 In Channel Flow: Mlb/hr 71.75 Active Channel Flow: Mlb/hr 69.69 Total Bypass Flow (%): 10.8 (of total core flow)
| |
| Total Water Rod Flow (%): 2.6 (of total core flow)
| |
| Source Convergence 0.00050 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.459 45 9 28 1.916 0.736 45 13 28 7.25 0.753 48.4 42 11 28 18 7.22 0.796 60.0 41 13 16 15 1.458 45 13 28 1.929 0.731 45 9 26 7.12 0.749 49.6 42 13 34 18 7.26 0.794 59.7 41 15 40 15 1.442 45 13 32 1.953 0.722 45 11 30 7.11 0.748 49.6 42 13 30 18 6.97 0.779 60.5 42 19 40 15 1.439 45 11 30 1.956 0.721 45 13 22 7.14 0.744 48.7 42 11 32 18 7.17 0.774 59.2 42 11 22 15 1.425 45 25 44 1.965 0.718 45 27 44 7.11 0.741 48.8 42 15 32 18 7.46 0.772 57.7 42 11 28 15 1.418 45 11 34 1.985 0.710 45 11 34 7.07 0.740 49.2 42 25 42 18 7.66 0.768 56.4 41 9 30 15 1.408 44 13 36 1.991 0.708 44 13 36 6.87 0.739 51.6 42 19 40 18 6.98 0.767 59.9 42 21 42 15 1.407 43 15 30 1.991 0.708 45 11 36 6.98 0.735 49.7 42 23 40 18 7.07 0.763 59.2 42 9 34 15 1.402 45 9 32 2.001 0.705 45 9 32 7.07 0.735 48.6 41 15 40 18 7.31 0.763 58.0 42 13 34 15 1.401 45 11 36 2.027 0.696 45 21 44 7.12 0.735 47.9 42 15 28 18 7.46 0.760 57.1 42 13 30 15
| |
| * LHGR calculated with pin-power reconstruction
| |
| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.64 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 20,200.0 MWd/MTU
| |
| | |
| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page A-68 Cycle: 23 Core Average Exposure: MWd/MTU 37354.8 Exposure: MWd/MTU (GWd) 20696.6 (2101.64 )
| |
| Delta E: MWd/MTU, (GWd) 496.6 ( 50.43 ) Axial Profile Edit Radial Power Power: MWt 2111.8 ( 72.25 %) N(PRA) Power Exposure Zone Avg. Max. IR JR Core Pressure: psia 1044.7 Top 25 0.299 7.722 37 0.673 0.703 3 24 Inlet Subcooling: Btu/lbm -20.83 24 0.694 19.246 38 0.347 0.564 5 16 Flow: Mlb/hr 80.46 (104.50 %) 23 1.158 27.921 39 0.378 0.750 17 48 22 1.348 32.870 40 0.432 0.905 5 34 2 6 10 14 18 22 26 30 34 38 42 46 50 21 1.444 35.657 41 0.820 1.230 9 30 51 -- -- -- -- -- 51 20 1.496* 37.669 42 1.095 1.226 11 28 47 -- -- -- -- -- -- -- -- -- 47 19 1.485 38.732 43 1.295 1.404 15 30 43 -- -- -- -- -- -- -- -- -- -- -- 43 18 1.469 39.978 44 1.258 1.415 13 36 39 -- -- -- -- -- -- -- -- -- -- -- 39 17 1.427 40.871 45 1.339 1.474 9 28 35 -- -- -- -- -- -- -- -- -- -- -- -- -- 35 16 1.372 41.316 31 -- -- -- -- -- -- -- -- -- -- -- -- -- 31 15 1.356 41.738 27 -- -- -- -- -- -- -- -- -- -- -- -- -- 27 14 1.299 42.065 23 -- -- -- -- -- -- -- -- -- -- -- -- -- 23 13 1.322 41.784 19 -- -- -- -- -- -- -- -- -- -- -- -- -- 19 12 1.278 43.080 15 -- -- -- -- -- -- -- -- -- -- -- 15 11 1.195 43.806 11 -- -- -- -- -- -- -- -- -- -- -- 11 10 1.144 43.319 7 -- -- -- -- -- -- -- -- -- 7 9 1.055 43.916 3 -- -- -- -- -- 3 8 0.929 44.263 2 6 10 14 18 22 26 30 34 38 42 46 50 7 0.794 44.584 6 0.665 45.174*
| |
| 5 0.545 44.991 4 0.449 43.554 Control Rod Density: % 0.00 3 0.383 40.717 2 0.304 32.055 k-effective: 0.99931 Bottom 1 0.090 9.451 Void Fraction: 0.269 Core Delta-P: psia 21.275 % AXIAL TILT 25.406 -8.450 Core Plate Delta-P: psia 16.744 AVG BOT 8ft/12ft 0.8611 1.0505 Coolant Temp: Deg-F 546.0 In Channel Flow: Mlb/hr 71.99 Active Channel Flow: Mlb/hr 70.01 Total Bypass Flow (%): 10.5 (of total core flow)
| |
| Total Water Rod Flow (%): 2.5 (of total core flow)
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| Source Convergence 0.00029 Top Ten Thermal Limits Summary - Sorted by Margin Power MCPR APLHGR LHGR Value FT IR JR Value Margin FT IR JR Value Margin Exp. FT IR JR K Value Margin Exp. FT IR JR K 1.474 45 9 28 2.138 0.660 45 13 28 6.59 0.692 49.4 42 11 28 18 6.46 0.731 60.9 41 13 16 15 1.462 45 13 28 2.145 0.657 45 9 26 6.46 0.686 50.5 42 13 34 18 6.54 0.730 60.4 41 15 40 15 1.446 45 11 30 2.171 0.649 45 11 30 6.43 0.684 50.6 42 13 30 18 6.19 0.710 61.4 42 19 40 15 1.445 45 13 32 2.370 0.647 42 11 28 6.49 0.683 49.7 42 11 32 18 6.90 0.709 57.4 41 9 30 15 1.436 45 25 44 2.185 0.645 45 13 22 6.41 0.678 50.1 42 25 42 18 6.38 0.706 60.2 42 11 22 15 1.428 45 11 34 2.188 0.644 45 27 44 6.61 0.676 47.1 41 9 30 18 6.65 0.706 58.6 42 11 28 15 1.415 45 9 32 2.205 0.639 45 11 34 6.22 0.676 52.5 42 19 40 18 6.21 0.701 60.8 42 21 42 15 1.415 44 13 36 2.405 0.638 42 13 30 6.50 0.676 48.5 41 13 38 18 6.33 0.700 60.1 42 9 34 15 1.414 45 11 36 2.211 0.638 45 11 36 6.43 0.676 49.5 41 15 40 18 6.51 0.697 58.9 42 13 34 15 1.404 43 15 30 2.216 0.636 44 13 36 6.41 0.675 49.8 42 15 32 18 6.63 0.693 58.1 42 13 30 15
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| * LHGR calculated with pin-power reconstruction
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| * CPR calculated with pin-power reconstruction & CPR limit type 3 Figure A.65 Brunswick Unit 1 Cycle 23 Control Rod Pattern and Axial Distributions at 20,696.6 MWd/MTU
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page B-1 Appendix B Elevation Views of the Brunswick Unit 1 Cycle 23 Fresh Reload Batch Fuel Assemblies
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page B-2 Figure B.1 Elevation View for the Brunswick Unit 1 Cycle 23 Fresh Fuel Reload Batch BRK1-23 ATRIUM 11 [ ] Fuel Assembly Design
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page B-3 Figure B.2 Elevation View for the Brunswick Unit 1 Cycle 23 Fresh Fuel Reload Batch BRK1-23 ATRIUM 11 [ ] Fuel Assembly Design
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page B-4 Figure B.3 Elevation View for the Brunswick Unit 1 Cycle 23 Fresh Fuel Reload Batch BRK1-23 ATRIUM 11 [ ] Fuel Assembly Design
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page C-1 Appendix C Brunswick Unit 1 Cycle 23 Fresh Fuel Locations
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page C-2 Table C.1 Brunswick Unit 1 Cycle 23 Reload Fuel Identification and Locations ( [ ])
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page C-3 Table C.2 Brunswick Unit 1 Cycle 23 Reload Fuel Identification and Locations ( [ ])
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page C-4 Table C.3 Brunswick Unit 1 Cycle 23 Reload Fuel Identification and Locations ( [ ])
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page D-1 Appendix D Brunswick Unit 1 Cycle 23 Radial Exposure and Power Distributions
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page D-2
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| ]
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| Figure D.1 Brunswick Unit 1 Cycle 23 BOC Exposure Distribution (GWd/MTU)
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page D-3
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| Figure D.1 Brunswick Unit 1 Cycle 23 BOC Exposure Distribution (GWd/MTU) (Continued)
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page D-4
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| Figure D.2 Brunswick Unit 1 Cycle 23 EOC Exposure Distribution (20.7 GWd/MTU)
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page D-5
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| Figure D.2 Brunswick Unit 1 Cycle 23 EOC Exposure Distribution (20.7 GWd/MTU) (Continued)
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page D-6
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| Figure D.3 Brunswick Unit 1 Cycle 23 Radial Power Distribution at 0.0 MWd/MTU
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page D-7
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| Figure D.3 Brunswick Unit 1 Cycle 23 Radial Power Distribution at 0.0 MWd/MTU (Continued)
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page D-8
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| Figure D.4 Brunswick Unit 1 Cycle 23 Radial Power Distribution at 19,343.7 MWd/MTU (EOFP)
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| Controlled Document Framatome Inc. ANP-3759NP Revision 2 Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report Page D-9
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| Figure D.4 Brunswick Unit 1 Cycle 23 Radial Power Distribution at 19,343.7 MWd/MTU (EOFP) (Continued)
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| RA-19-0411 Enclosure 8 ANP-3758NP, Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report, Revision 1
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| Controlled Document 0414-12-F04 (Rev. 003, 09/17/2018)
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| Brunswick Unit 1 Cycle 23 ANP-3758NP Revision 1 ATRIUM 11 Fuel Nuclear Fuel Design Report September 2019
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| © 2019 Framatome Inc.
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| Controlled Document ANP-3758NP Revision 1 Copyright © 2019 Framatome Inc.
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| All Rights Reserved FRAMATOME INC. PROPRIETARY This document and any information contained herein is the property of Framatome Inc. (Framatome) and is to be considered proprietary and may not be reproduced or copied in whole or in part. This document shall not be furnished to others without the express written consent of Framatome and is not to be used in any way which is or may be detrimental to Framatome. This document and any copies that may have been made must be returned to Framatome upon request.
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| ATRIUM and Z4B are trademarks or registered trademarks of Framatome or its affiliates, in the USA or other countries.
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page i Nature of Changes Section(s) or Item Page(s) Description and Justification 1 1-1 Last paragraph updated number of assemblies and changed Reference 7 to per Brunswick Unit 1 Cycle 23 redesign.
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| 2 3-1 Updated Reference 1 and removed Reference 7
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page ii Contents Page
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| ==1.0 INTRODUCTION==
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| ..........................................................................................................1-1 2.0 NEUTRONIC DESIGN .................................................................................................2-1 2.1 Neutronic Design Description ............................................................................2-1 2.2 Lattice Control Blade Worths and Kinetics Parameters .....................................2-2 2.3 Enriched Lattice Uncontrolled Reactivities and Isotopic Data ............................2-2 2.4 Criticality Compliance .......................................................................................2-2
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| ==3.0 REFERENCES==
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| .............................................................................................................3-1 Appendix A Enriched Lattice Hot Uncontrolled Reactivity and LPF Plots.......................... A-1 Appendix B Enriched Lattice Hot Uncontrolled Reactivity and LPF Tables ....................... B-1 Appendix C Enriched Lattice Isotopic Data Tables ........................................................... C-1 Appendix D Lattice Enrichment Distribution Maps ............................................................ D-1
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page iii List of Tables Table 2.1 Neutronic Design Parameters ..............................................................................2-3 Table 2.2 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment .....................................................................2-9 Table 2.3 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-10 Table 2.4 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-11 Table 2.5 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-12 Table 2.6 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-13 Table 2.7 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-14 Table 2.8 Lattice [ ] Kinetics Parameters at BOL .............................2-14 Table 2.9 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-15 Table 2.10 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-16 Table 2.11 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-17 Table 2.12 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-18 Table 2.13 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-19 Table 2.14 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-20 Table 2.15 Lattice [ ] Kinetics Parameters at BOL ...............................2-20 Table 2.16 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-21 Table 2.17 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-22 Table 2.18 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-23 Table 2.19 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-24 Table 2.20 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-25 Table 2.21 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-26 Table 2.22 Lattice [ ] Kinetics Parameters at BOL ............................2-26 Table 2.23 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-27 Table 2.24 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-28
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page iv Table 2.25 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-29 Table 2.26 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-30 Table 2.27 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-31 Table 2.28 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-32 Table 2.29 Lattice [ ] Kinetics Parameters at BOL ............................2-32 Table 2.30 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-33 Table 2.31 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-34 Table 2.32 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-35 Table 2.33 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-36 Table 2.34 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-37 Table 2.35 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-38 Table 2.36 Lattice [ ] Kinetics Parameters at BOL...........................2-38 Table 2.37 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-39 Table 2.38 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-40 Table 2.39 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-41 Table 2.40 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-42 Table 2.41 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-43 Table 2.42 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-44 Table 2.43 Lattice [ ] Kinetics Parameters at BOL .............................2-44 Table 2.44 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-45 Table 2.45 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-46 Table 2.46 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-47 Table 2.47 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-48 Table 2.48 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-49 Table 2.49 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-50
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page v Table 2.50 Lattice [ ] Kinetics Parameters at BOL ...............................2-50 Table 2.51 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-51 Table 2.52 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-52 Table 2.53 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-53 Table 2.54 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-54 Table 2.55 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-55 Table 2.56 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-56 Table 2.57 Lattice [ ] Kinetics Parameters at BOL .............................2-56 Table 2.58 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-57 Table 2.59 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-58 Table 2.60 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-59 Table 2.61 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-60 Table 2.62 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-61 Table 2.63 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-62 Table 2.64 Lattice [ ] Kinetics Parameters at BOL ...............................2-62 Table 2.65 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-63 Table 2.66 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-64 Table 2.67 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-65 Table 2.68 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-66 Table 2.69 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-67 Table 2.70 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-68 Table 2.71 Lattice [ ] Kinetics Parameters at BOL ............................2-68 Table 2.72 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-69 Table 2.73 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-70 Table 2.74 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-71
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page vi Table 2.75 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-72 Table 2.76 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-73 Table 2.77 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-74 Table 2.78 Lattice [ ] Kinetics Parameters at BOL...............................2-74 Table 2.79 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-75 Table 2.80 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-76 Table 2.81 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-77 Table 2.82 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-78 Table 2.83 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-79 Table 2.84 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-80 Table 2.85 Lattice [ ] Kinetics Parameters at BOL .............................2-80 Table 2.86 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-81 Table 2.87 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-82 Table 2.88 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-83 Table 2.89 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-84 Table 2.90 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-85 Table 2.91 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-86 Table 2.92 Lattice [ ] Kinetics Parameters at BOL ...............................2-86 Table 2.93 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-87 Table 2.94 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-88 Table 2.95 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-89 Table 2.96 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-90 Table 2.97 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-91 Table 2.98 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-92 Table 2.99 Lattice [ ] Kinetics Parameters at BOL ...............................2-92
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page vii Table 2.100 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-93 Table 2.101 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ....................................................................................2-94 Table 2.102 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .........................................................2-95 Table 2.103 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP.............................................2-96 Table 2.104 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ........................................................2-97 Table 2.105 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 ...............................................................2-98 Table 2.106 Lattice [ ] Kinetics Parameters at BOL...............................2-98 Table 2.107 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment ...................................................................2-99 Table 2.108 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ..................................................................................2-100 Table 2.109 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .......................................................2-101 Table 2.110 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP...........................................2-102 Table 2.111 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ......................................................2-103 Table 2.112 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 .............................................................2-104 Table 2.113 Lattice [ ] Kinetics Parameters at BOL ...........................2-104 Table 2.114 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment .................................................................2-105 Table 2.115 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ..................................................................................2-106 Table 2.116 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .......................................................2-107 Table 2.117 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP...........................................2-108 Table 2.118 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ......................................................2-109 Table 2.119 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 .............................................................2-110 Table 2.120 Lattice [ ] Kinetics Parameters at BOL .............................2-110 Table 2.121 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment .................................................................2-111 Table 2.122 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 ..................................................................................2-112 Table 2.123 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 .......................................................2-113 Table 2.124 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP...........................................2-114
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page viii Table 2.125 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP ......................................................2-115 Table 2.126 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 .............................................................2-116 Table 2.127 Lattice [ ] Kinetics Parameters at BOL .............................2-116 List of Figures Figure 2.1 Assembly Type [ ] ...........................................................2-117 Figure 2.2 Assembly Type [ ] ...........................................................2-118 Figure 2.3 Assembly Type [ ] ..........................................................2-119 Figure 2.4 [ ] Fuel Rod Distribution ..................................................2-120 Figure 2.5 [ ] Fuel Rod Distribution ..................................................2-121 Figure 2.6 [ ] Fuel Rod Distribution ..................................................2-122 Figure 2.7 Fuel Rod Axial Description ................................................................................2-123
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page ix Nomenclature Acronym Definition
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| [] Square brackets enclose information that is proprietary to Framatome.
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| BOL beginning of life BWR boiling water reactor EVC plenum region in a fuel pin modeled as an evacuated section GWd/MTU gigawatt days per metric ton of initial uranium kg/MTU kilograms per metric ton of initial uranium LHGR linear heat generation rate LPF local peaking factor MCPR minimum critical power ratio MWd/MTU megawatt days per metric ton of initial uranium NRC (United States) Nuclear Regulatory Commission PLFR part length fuel rod Z4B Zirconium-based alloy proprietary to Framatome Inc.
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 1-1
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| ==1.0 INTRODUCTION==
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| This report provides results of the neutronic design analyses performed by Framatome Inc. for the Brunswick Unit 1 fabrication batch BRK1-23 ATRIUM 11 boiling water reactor (BWR) fuel assemblies scheduled to be loaded in Cycle 23. The mechanical design parameters for the fuel are from Reference 1 and are shown in Table 2.1.
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| Applicable neutronic design criteria are provided in the approved topical report ANF 98(P)(A) Revision 1 and Supplement 1 (Reference 2). Neutronic design analysis methodology used to determine conformance to design criteria has been reviewed and approved by the NRC in the topical report EMF-2158(P)(A) (Reference 3).
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| The fuel design includes Framatome Inc. advanced fuel channels. Mechanical design criteria applicable to the design of these channels have been reviewed and approved by the NRC. Reference 1 provides details of the application of the advanced channel for Brunswick Unit 1. The fuel design assumes advanced fuel channels made of Zircaloy-4 and/or Z4B with a beta quench treatment.
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| The neutronic design for the fabrication batch includes axially-varying enrichment and gadolinia designs with natural UO2 blankets at the top and bottom of the assembly. The fabrication batch consists of [
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| ] assemblies (per Brunswick Unit 1 Cycle 23 redesign).
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| Pertinent fuel and reactor core design information associated with this fabrication batch is given in Section 2.0 and in Appendices A through D.
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-1 2.0 NEUTRONIC DESIGN The results of the Brunswick Unit 1 fabrication batch BRK1-23 ATRIUM 11 neutronic design analyses are presented in this section. The fuel was designed to meet applicable design criteria, as well as reactivity and control requirements. Reactor core loading patterns and the number of assemblies to be loaded will depend upon final cycle energy requirements as specified by the utility. Applicable neutronic design criteria outlined in Reference 2 are summarized below:
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| * Power Distribution. The local power distribution in the fuel assembly combined with the core power distribution shall result in Linear Heat Generation Rate (LHGR) and Minimum Critical Power Ratio (MCPR) values that are within the limits established for each fuel design.
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| * Kinetics Parameters. The moderator void reactivity coefficient due to boiling in the active channels and the Doppler fuel temperature reactivity coefficient shall be negative.
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| The negative void and Doppler reactivity coefficients ensure a negative power coefficient during reactor operation. Additional calculations were performed to show that the assembly average Doppler and void reactivity coefficients remain negative for the life of the assembly. These results demonstrate that the Reference 2 kinetics criteria are met on a bundle average basis.
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| * Control Blade Reactivity. The design of the fuel assembly and the reactor core loading shall be such that the technical specification shutdown margin requirement is met for all reactor conditions.
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| 2.1 Neutronic Design Description The neutronic design parameters for fabrication batch BRK1-23 are presented in Table 2.1.
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| The key ATRIUM 11 reload assembly nuclear design characteristics are summarized below:
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| * Each fuel assembly has top and bottom natural uranium blankets.
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| * The plenum region above the PLFRs will be explicitly modeled.
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| * The enrichments are designed to yield a local power distribution which results in a balanced design relative to MCPR, LHGR, and other reactor operating requirements, e.g., power peaking.
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| * Gadolinia (Gd2O3 blended with UO2) rods are designed to control assembly reactivity in order to meet reactivity control requirements in the reactor, e.g. cold shutdown margin.
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| * The reload batch consists of 3 assembly designs which vary axially in enrichment and/or gadolinia. The axial distributions of the lattices in the assemblies are shown in Figures 2.1, 2.2, and 2.3. The fuel rod distribution and axial descriptions are presented in Figures 2.4 through 2.7. The enrichment and gadolinia distribution maps for each of the reload assembly lattices are displayed in Appendix D.
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-2
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| * The fuel assembly incorporates the Framatome Inc. advanced fuel channel which improves uranium utilization. For D-lattice plants, the fuel assembly is offset 40 mils toward the control blade.
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| 2.2 Lattice Control Blade Worths and Kinetics Parameters Beginning of life (BOL) lattice reactivities (k) have been calculated for moderator and fuel conditions ranging from cold to hot operating conditions. From these reactivities, BOL control blade worths and kinetics parameters have been determined based on GE Original Equipment, Duralife 160, Westinghouse-ABB CR82M-1, Westinghouse-ABB CR82M-1 HF TIP, Westinghouse-ABB CR99 TIP, and Westinghouse-ABB CR99 control blades. Kinetics parameters are calculated for fuel temperature (Doppler), moderator void, and moderator temperature. The Doppler reactivity was calculated over a fuel temperature range from hot standby to hot operating. The moderator void reactivity was evaluated between the 0% and 40% voided hot operating cases, and the moderator temperature reactivity was calculated from the cold to hot standby condition. The calculations neglect the spacer material and assume zero void in the coolant outside the fuel assembly channel as well as inside the internal water channel. The results of these calculations are presented in Tables 2.2 through 2.127.
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| 2.3 Enriched Lattice Uncontrolled Reactivities and Isotopic Data The enriched lattice exposure-dependent uncontrolled reactivities calculated at three void fractions are presented graphically in Appendix A, and in tabular format in Appendix B. The enriched lattice exposure-dependent isotopic data calculated at three void fractions are presented in Appendix C.
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| 2.4 Criticality Compliance The Brunswick Unit 1 fabrication batch BRK1-23 ATRIUM 11 fuel assemblies satisfy the fuel design critical safety limits established for new and spent fuel storage at the Brunswick Unit 1 facility per References 4 and 5. Additionally, these reload assemblies conform to the nuclear criticality requirements as provided to the NRC for the Reference 6 shipping container.
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-3 Table 2.1 Neutronic Design Parameters
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-4 Table 2.1 Neutronic Design Parameters (Continued)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-5 Table 2.1 Neutronic Design Parameters (Continued)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-6 Table 2.1 Neutronic Design Parameters (Continued)
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| Parameter Design Value Control Blade Data for Westinghouse-ABB CR82M-1 Total span, cm Westinghouse Proprietary Total support span, cm Total thickness, cm Total face-to-face internal dimension, inch B4C rod absorber Number of rods Diameter of rod, cm Diameter of sheath, inch Theoretical density B4C, %
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| B4C zone span, cm Control Blade Data for Westinghouse-ABB CR82M-1 HF TIP Total span, cm Westinghouse Proprietary Total support span, cm Total thickness, cm Total face-to-face internal dimension, inch Hafnium rod absorber Number of rods Diameter of rod, cm Diameter of sheath, inch Hafnium rod zone span, cm
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-7 Table 2.1 Neutronic Design Parameters (Continued)
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| Parameter Design Value Control Blade Data for Westinghouse-ABB CR99 TIP Total span, cm Westinghouse Proprietary Total support span, cm Total thickness, cm Total face-to-face internal dimension, inch B4C rod absorber Number of rods Diameter of rod, cm Diameter of sheath, inch Theoretical density B4C, %
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| B4C zone span, cm Control Blade Data for Westinghouse-ABB CR99 Total span, cm Westinghouse Proprietary Total support span, cm Total thickness, cm Total face-to-face internal dimension, inch B4C rod absorber Number of rods Diameter of rod, cm Diameter of sheath, inch Theoretical density B4C, %
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| B4C zone span, cm
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-8 Table 2.1 Neutronic Design Parameters (Continued)
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| Parameter Design Value Core Data*
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| Number of fuel assemblies in the core 560 Rated thermal power level, MWt 2923.0 Rated core flow, Mlbm/hr 77.00 Inlet subcooling, Btu/lbm 21.3 Dome pressure, psia 1045.0 Boron concentration, PPM 720.0 Intermediate temperature, °F 200.00 Warm temperature, °F 360.00
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| * Some values are representative of rated conditions and may vary depending on the core statepoint.
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-9 Table 2.2 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92137 1.09637 -0.1596 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90804 1.08820 -0.1656 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85765 1.05923 -0.1903 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.85373 1.05445 -0.1904 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.85380 1.05445 -0.1903 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.81623 1.03844 -0.2140 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.77229 1.02081 -0.2434 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-10 Table 2.3 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92090 1.09637 -0.1600 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90764 1.08820 -0.1659 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85725 1.05923 -0.1907 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.85333 1.05445 -0.1907 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.85339 1.05445 -0.1907 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.81537 1.03844 -0.2148 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.77065 1.02081 -0.2451 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-11 Table 2.4 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91571 1.09637 -0.1648 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90244 1.08820 -0.1707 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85087 1.05923 -0.1967 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.84700 1.05445 -0.1967 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.84708 1.05445 -0.1967 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.80802 1.03844 -0.2219 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.76160 1.02081 -0.2539 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-12 Table 2.5 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93767 1.09637 -0.1447 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92512 1.08820 -0.1499 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87855 1.05923 -0.1706 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.87451 1.05445 -0.1706 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.87451 1.05445 -0.1706 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.84053 1.03844 -0.1906 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.80093 1.02081 -0.2154 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-13 Table 2.6 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91329 1.09637 -0.1670 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89982 1.08820 -0.1731 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84716 1.05923 -0.2002 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.84330 1.05445 -0.2003 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.84338 1.05445 -0.2002 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.80268 1.03844 -0.2270 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.75378 1.02081 -0.2616 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-14 Table 2.7 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91151 1.09637 -0.1686 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89798 1.08820 -0.1748 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84493 1.05923 -0.2023 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.84108 1.05445 -0.2024 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.84117 1.05445 -0.2023 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.80005 1.03844 -0.2296 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.75060 1.02081 -0.2647 80% Void Table 2.8 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.05445 1.05923 -0.0045 1.03844 1.05445 -0.0152 1.05923 1.09637 -0.0339
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-15 Table 2.9 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.97979 1.16169 -0.1566 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.96573 1.15364 -0.1629 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.90847 1.12049 -0.1892 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.90424 1.11537 -0.1893 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.90432 1.11537 -0.1892 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.85962 1.09453 -0.2146 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.80532 1.07061 -0.2478 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-16 Table 2.10 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.97914 1.16169 -0.1571 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.96517 1.15364 -0.1634 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.90795 1.12049 -0.1897 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.90372 1.11537 -0.1898 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.90379 1.11537 -0.1897 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.85865 1.09453 -0.2155 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.80361 1.07061 -0.2494 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-17 Table 2.11 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.97375 1.16169 -0.1618 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.95974 1.15364 -0.1681 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.90109 1.12049 -0.1958 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.89691 1.11537 -0.1959 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.89701 1.11537 -0.1958 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.85072 1.09453 -0.2228 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.79405 1.07061 -0.2583 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-18 Table 2.12 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.99779 1.16169 -0.1411 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.98452 1.15364 -0.1466 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.93104 1.12049 -0.1691 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.92668 1.11537 -0.1692 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.92668 1.11537 -0.1692 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.88565 1.09453 -0.1908 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.83586 1.07061 -0.2193 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-19 Table 2.13 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.97110 1.16169 -0.1641 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.95687 1.15364 -0.1706 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.89718 1.12049 -0.1993 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.89302 1.11537 -0.1993 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.89311 1.11537 -0.1993 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.84517 1.09453 -0.2278 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.78594 1.07061 -0.2659 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-20 Table 2.14 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.96909 1.16169 -0.1658 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.95481 1.15364 -0.1724 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.89471 1.12049 -0.2015 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.89057 1.11537 -0.2016 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.89066 1.11537 -0.2015 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.84227 1.09453 -0.2305 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.78245 1.07061 -0.2692 80% Void Table 2.15 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.11537 1.12049 -0.0046 1.09453 1.11537 -0.0187 1.12049 1.16169 -0.0355
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-21 Table 2.16 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93860 1.12073 -0.1625 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92572 1.11425 -0.1692 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87499 1.08892 -0.1965 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.87082 1.08383 -0.1965 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.87089 1.08383 -0.1965 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.82958 1.06735 -0.2228 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.77724 1.04750 -0.2580 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-22 Table 2.17 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93810 1.12073 -0.1630 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92533 1.11425 -0.1696 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87467 1.08892 -0.1968 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.87051 1.08383 -0.1968 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.87057 1.08383 -0.1968 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.82880 1.06735 -0.2235 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.77564 1.04750 -0.2595 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-23 Table 2.18 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93248 1.12073 -0.1680 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91970 1.11425 -0.1746 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86781 1.08892 -0.2031 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.86370 1.08383 -0.2031 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.86379 1.08383 -0.2030 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.82089 1.06735 -0.2309 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.76601 1.04750 -0.2687 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-24 Table 2.19 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.95578 1.12073 -0.1472 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.94380 1.11425 -0.1530 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.89725 1.08892 -0.1760 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.89296 1.08383 -0.1761 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.89296 1.08383 -0.1761 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.85550 1.06735 -0.1985 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.80802 1.04750 -0.2286 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-25 Table 2.20 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93021 1.12073 -0.1700 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91720 1.11425 -0.1769 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86420 1.08892 -0.2064 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.86011 1.08383 -0.2064 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.86019 1.08383 -0.2063 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.81564 1.06735 -0.2358 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.75824 1.04750 -0.2761 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-26 Table 2.21 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92825 1.12073 -0.1718 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91518 1.11425 -0.1787 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86177 1.08892 -0.2086 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.85769 1.08383 -0.2087 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.85777 1.08383 -0.2086 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.81276 1.06735 -0.2385 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.75472 1.04750 -0.2795 80% Void Table 2.22 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.08383 1.08892 -0.0047 1.06735 1.08383 -0.0152 1.08892 1.12073 -0.0284
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-27 Table 2.23 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93065 1.10611 -0.1586 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91749 1.09947 -0.1655 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86667 1.07495 -0.1938 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.86258 1.06997 -0.1938 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.86265 1.06997 -0.1938 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.82119 1.05387 -0.2208 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.76782 1.03366 -0.2572 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-28 Table 2.24 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93023 1.10611 -0.1590 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91717 1.09947 -0.1658 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86646 1.07495 -0.1940 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.86238 1.06997 -0.1940 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.86244 1.06997 -0.1940 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.82053 1.05387 -0.2214 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.76633 1.03366 -0.2586 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-29 Table 2.25 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92451 1.10611 -0.1642 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91144 1.09947 -0.1710 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85954 1.07495 -0.2004 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.85552 1.06997 -0.2004 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.85560 1.06997 -0.2004 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.81258 1.05387 -0.2290 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.75669 1.03366 -0.2680 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-30 Table 2.26 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.94669 1.10611 -0.1441 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.93442 1.09947 -0.1501 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.88790 1.07495 -0.1740 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.88369 1.06997 -0.1741 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.88369 1.06997 -0.1741 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.84619 1.05387 -0.1971 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.79786 1.03366 -0.2281 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-31 Table 2.27 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92270 1.10611 -0.1658 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90940 1.09947 -0.1729 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85637 1.07495 -0.2033 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.85235 1.06997 -0.2034 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.85243 1.06997 -0.2033 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.80774 1.05387 -0.2336 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.74924 1.03366 -0.2752 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-32 Table 2.28 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92084 1.10611 -0.1675 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90748 1.09947 -0.1746 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85404 1.07495 -0.2055 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.85004 1.06997 -0.2056 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.85012 1.06997 -0.2055 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.80496 1.05387 -0.2362 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.74581 1.03366 -0.2785 80% Void Table 2.29 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.06997 1.07495 -0.0046 1.05387 1.06997 -0.0150 1.07495 1.10611 -0.0282
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-33 Table 2.30 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90274 1.08035 -0.1644 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.88906 1.07315 -0.1715 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.83846 1.04869 -0.2005 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.83437 1.04366 -0.2005 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.83444 1.04366 -0.2005 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79501 1.02973 -0.2279 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.74285 1.01135 -0.2655 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-34 Table 2.31 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90236 1.08035 -0.1648 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.88881 1.07315 -0.1718 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.83833 1.04869 -0.2006 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.83425 1.04366 -0.2006 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.83431 1.04366 -0.2006 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79443 1.02973 -0.2285 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.74145 1.01135 -0.2669 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-35 Table 2.32 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.89675 1.08035 -0.1699 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.88319 1.07315 -0.1770 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.83160 1.04869 -0.2070 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.82757 1.04366 -0.2071 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.82765 1.04366 -0.2070 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.78668 1.02973 -0.2360 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.73202 1.01135 -0.2762 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-36 Table 2.33 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91877 1.08035 -0.1496 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90602 1.07315 -0.1557 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85978 1.04869 -0.1801 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.85557 1.04366 -0.1802 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.85557 1.04366 -0.1802 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.82014 1.02973 -0.2035 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.77316 1.01135 -0.2355 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-37 Table 2.34 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.89486 1.08035 -0.1717 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.88109 1.07315 -0.1790 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.82845 1.04869 -0.2100 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.82443 1.04366 -0.2101 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.82451 1.04366 -0.2100 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.78192 1.02973 -0.2407 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.72467 1.01135 -0.2835 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-38 Table 2.35 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.89300 1.08035 -0.1734 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.87918 1.07315 -0.1807 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.82612 1.04869 -0.2122 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.82212 1.04366 -0.2123 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.82220 1.04366 -0.2122 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.77913 1.02973 -0.2434 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.72122 1.01135 -0.2869 80% Void Table 2.36 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.04366 1.04869 -0.0048 1.02973 1.04366 -0.0134 1.04869 1.08035 -0.0293
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-39 Table 2.37 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90236 1.07395 -0.1598 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.88855 1.06673 -0.1670 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.83876 1.04367 -0.1963 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.83477 1.03879 -0.1964 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.83484 1.03879 -0.1963 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79554 1.02603 -0.2246 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.74201 1.00830 -0.2641 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-40 Table 2.38 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90200 1.07395 -0.1601 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.88832 1.06673 -0.1673 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.83868 1.04367 -0.1964 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.83469 1.03879 -0.1965 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.83475 1.03879 -0.1964 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79502 1.02603 -0.2251 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.74067 1.00830 -0.2654 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-41 Table 2.39 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.89670 1.07395 -0.1650 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.88300 1.06673 -0.1722 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.83228 1.04367 -0.2025 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.82834 1.03879 -0.2026 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.82842 1.03879 -0.2025 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.78757 1.02603 -0.2324 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.73144 1.00830 -0.2746 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-42 Table 2.40 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91773 1.07395 -0.1455 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90484 1.06673 -0.1518 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85947 1.04367 -0.1765 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.85537 1.03879 -0.1766 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.85537 1.03879 -0.1766 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.82024 1.02603 -0.2006 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.77222 1.00830 -0.2341 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-43 Table 2.41 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.89493 1.07395 -0.1667 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.88104 1.06673 -0.1741 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.82932 1.04367 -0.2054 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.82539 1.03879 -0.2054 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.82547 1.03879 -0.2054 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.78303 1.02603 -0.2368 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.72427 1.00830 -0.2817 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-44 Table 2.42 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.89315 1.07395 -0.1683 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.87920 1.06673 -0.1758 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.82707 1.04367 -0.2075 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.82316 1.03879 -0.2076 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.82323 1.03879 -0.2075 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.78030 1.02603 -0.2395 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.72084 1.00830 -0.2851 80% Void Table 2.43 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.03879 1.04367 -0.0047 1.02603 1.03879 -0.0123 1.04367 1.07395 -0.0282
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-45 Table 2.44 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91327 1.08519 -0.1584 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90015 1.07886 -0.1656 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85388 1.06074 -0.1950 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84989 1.05587 -0.1951 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84996 1.05587 -0.1950 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.81208 1.04582 -0.2235 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.75962 1.03154 -0.2636 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-46 Table 2.45 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91289 1.08519 -0.1588 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89990 1.07886 -0.1659 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85378 1.06074 -0.1951 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84980 1.05587 -0.1952 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84986 1.05587 -0.1951 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.81152 1.04582 -0.2240 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.75821 1.03154 -0.2650 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-47 Table 2.46 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90754 1.08519 -0.1637 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89453 1.07886 -0.1709 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84727 1.06074 -0.2013 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84334 1.05587 -0.2013 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84342 1.05587 -0.2012 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.80389 1.04582 -0.2313 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.74868 1.03154 -0.2742 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-48 Table 2.47 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92876 1.08519 -0.1442 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91657 1.07886 -0.1504 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87487 1.06074 -0.1752 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.87078 1.05587 -0.1753 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.87078 1.05587 -0.1753 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.83724 1.04582 -0.1994 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.79062 1.03154 -0.2336 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-49 Table 2.48 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90581 1.08519 -0.1653 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89260 1.07886 -0.1726 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84433 1.06074 -0.2040 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84041 1.05587 -0.2041 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84048 1.05587 -0.2040 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79935 1.04582 -0.2357 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.74145 1.03154 -0.2812 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-50 Table 2.49 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90401 1.08519 -0.1670 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89075 1.07886 -0.1744 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84205 1.06074 -0.2062 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.83814 1.05587 -0.2062 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.83822 1.05587 -0.2061 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79657 1.04582 -0.2383 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.73793 1.03154 -0.2846 80% Void Table 2.50 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.05587 1.06074 -0.0046 1.04582 1.05587 -0.0095 1.06074 1.08519 -0.0225
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-51 Table 2.51 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92837 1.10682 -0.1612 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91521 1.09887 -0.1671 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86467 1.06903 -0.1912 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.86072 1.06422 -0.1912 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.86079 1.06422 -0.1911 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.82314 1.04771 -0.2143 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.77929 1.02961 -0.2431 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-52 Table 2.52 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92788 1.10682 -0.1617 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91480 1.09887 -0.1675 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86423 1.06903 -0.1916 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.86029 1.06422 -0.1916 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.86035 1.06422 -0.1916 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.82226 1.04771 -0.2152 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.77763 1.02961 -0.2447 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-53 Table 2.53 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92270 1.10682 -0.1663 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90963 1.09887 -0.1722 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85792 1.06903 -0.1975 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.85402 1.06422 -0.1975 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.85410 1.06422 -0.1974 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.81499 1.04771 -0.2221 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.76870 1.02961 -0.2534 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-54 Table 2.54 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.94515 1.10682 -0.1461 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.93280 1.09887 -0.1511 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.88605 1.06903 -0.1712 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.88198 1.06422 -0.1712 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.88198 1.06422 -0.1712 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.84788 1.04771 -0.1907 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.80829 1.02961 -0.2150 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-55 Table 2.55 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92000 1.10682 -0.1688 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90670 1.09887 -0.1749 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85385 1.06903 -0.2013 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.84996 1.06422 -0.2013 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.85004 1.06422 -0.2013 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.80926 1.04771 -0.2276 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.76045 1.02961 -0.2614 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-56 Table 2.56 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91818 1.10682 -0.1704 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90483 1.09887 -0.1766 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85158 1.06903 -0.2034 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.84771 1.06422 -0.2034 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.84779 1.06422 -0.2034 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.80659 1.04771 -0.2301 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.75724 1.02961 -0.2645 80% Void Table 2.57 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.06422 1.06903 -0.0045 1.04771 1.06422 -0.0155 1.06903 1.10682 -0.0341
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-57 Table 2.58 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.98654 1.17158 -0.1579 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.97264 1.16367 -0.1642 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.91508 1.12937 -0.1897 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.91081 1.12421 -0.1898 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.91089 1.12421 -0.1898 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.86602 1.10266 -0.2146 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.81179 1.07803 -0.2470 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-58 Table 2.59 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.98587 1.17158 -0.1585 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.97205 1.16367 -0.1647 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.91452 1.12937 -0.1902 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.91027 1.12421 -0.1903 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.91033 1.12421 -0.1903 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.86503 1.10266 -0.2155 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.81006 1.07803 -0.2486 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-59 Table 2.60 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.98051 1.17158 -0.1631 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.96667 1.16367 -0.1693 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.90773 1.12937 -0.1963 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.90353 1.12421 -0.1963 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.90362 1.12421 -0.1962 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.85718 1.10266 -0.2226 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.80060 1.07803 -0.2574 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-60 Table 2.61 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 1.00499 1.17158 -0.1422 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.99190 1.16367 -0.1476 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.93807 1.12937 -0.1694 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.93368 1.12421 -0.1695 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.93368 1.12421 -0.1695 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.89241 1.10266 -0.1907 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.84258 1.07803 -0.2184 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-61 Table 2.62 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.97756 1.17158 -0.1656 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.96348 1.16367 -0.1720 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.90347 1.12937 -0.2000 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.89928 1.12421 -0.2001 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.89937 1.12421 -0.2000 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.85125 1.10266 -0.2280 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.79209 1.07803 -0.2652 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-62 Table 2.63 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.97552 1.17158 -0.1673 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.96139 1.16367 -0.1738 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.90096 1.12937 -0.2023 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=932° F 0.89679 1.12421 -0.2023 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=932° F 0.89688 1.12421 -0.2022 0% Void Hot Operating40 TModerator=550° F TFuel=932° F 0.84833 1.10266 -0.2306 40% Void Hot Operating 80 TModerator=550° F TFuel=932° F 0.78859 1.07803 -0.2685 80% Void Table 2.64 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.12421 1.12937 -0.0046 1.10266 1.12421 -0.0192 1.12937 1.17158 -0.0360
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-63 Table 2.65 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.94744 1.13334 -0.1640 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.93473 1.12704 -0.1706 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.88358 1.10042 -0.1971 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.87937 1.09528 -0.1971 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.87945 1.09528 -0.1971 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.83783 1.07797 -0.2228 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.78532 1.05714 -0.2571 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-64 Table 2.66 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.94692 1.13334 -0.1645 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.93431 1.12704 -0.1710 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.88323 1.10042 -0.1974 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.87903 1.09528 -0.1974 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.87909 1.09528 -0.1974 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.83702 1.07797 -0.2235 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.78369 1.05714 -0.2587 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-65 Table 2.67 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.94137 1.13334 -0.1694 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92878 1.12704 -0.1759 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87649 1.10042 -0.2035 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.87234 1.09528 -0.2036 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.87243 1.09528 -0.2035 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.82924 1.07797 -0.2307 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.77420 1.05714 -0.2676 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-66 Table 2.68 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.96519 1.13334 -0.1484 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.95341 1.12704 -0.1541 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.90641 1.10042 -0.1763 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.90208 1.09528 -0.1764 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.90208 1.09528 -0.1764 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.86426 1.07797 -0.1983 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.81648 1.05714 -0.2276 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-67 Table 2.69 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93873 1.13334 -0.1717 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92587 1.12704 -0.1785 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87242 1.10042 -0.2072 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.86829 1.09528 -0.2072 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.86838 1.09528 -0.2072 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.82352 1.07797 -0.2361 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.76595 1.05714 -0.2754 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-68 Table 2.70 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93673 1.13334 -0.1735 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92381 1.12704 -0.1803 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86995 1.10042 -0.2094 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.86584 1.09528 -0.2095 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.86592 1.09528 -0.2094 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.82060 1.07797 -0.2387 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.76241 1.05714 -0.2788 80% Void Table 2.71 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.09528 1.10042 -0.0047 1.07797 1.09528 -0.0158 1.10042 1.13334 -0.0290
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-69 Table 2.72 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.94748 1.13120 -0.1624 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.93475 1.12507 -0.1692 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.88432 1.09975 -0.1959 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.88018 1.09471 -0.1960 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.88026 1.09471 -0.1959 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.83858 1.07777 -0.2219 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.78506 1.05677 -0.2571 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-70 Table 2.73 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.94700 1.13120 -0.1628 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.93439 1.12507 -0.1695 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.88405 1.09975 -0.1961 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.87992 1.09471 -0.1962 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.87998 1.09471 -0.1961 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.83784 1.07777 -0.2226 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.78350 1.05677 -0.2586 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-71 Table 2.74 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.94144 1.13120 -0.1678 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92884 1.12507 -0.1744 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87740 1.09975 -0.2022 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.87332 1.09471 -0.2022 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.87340 1.09471 -0.2022 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.83017 1.07777 -0.2297 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.77410 1.05677 -0.2675 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-72 Table 2.75 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.96479 1.13120 -0.1471 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.95301 1.12507 -0.1529 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.90689 1.09975 -0.1754 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.90262 1.09471 -0.1755 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.90262 1.09471 -0.1755 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.86485 1.07777 -0.1976 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.81622 1.05677 -0.2276 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-73 Table 2.76 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93886 1.13120 -0.1700 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92598 1.12507 -0.1770 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87329 1.09975 -0.2059 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.86922 1.09471 -0.2060 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.86930 1.09471 -0.2059 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.82435 1.07777 -0.2351 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.76568 1.05677 -0.2754 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-74 Table 2.77 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93691 1.13120 -0.1718 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92398 1.12507 -0.1787 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87087 1.09975 -0.2081 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.86681 1.09471 -0.2082 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.86690 1.09471 -0.2081 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.82148 1.07777 -0.2378 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.76217 1.05677 -0.2788 80% Void Table 2.78 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.09471 1.09975 -0.0046 1.07777 1.09471 -0.0155 1.09975 1.13120 -0.0278
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-75 Table 2.79 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92064 1.10682 -0.1682 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90748 1.10025 -0.1752 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85748 1.07528 -0.2026 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.85333 1.07017 -0.2026 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.85341 1.07017 -0.2026 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.81384 1.05560 -0.2290 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.76163 1.03672 -0.2653 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-76 Table 2.80 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92021 1.10682 -0.1686 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90718 1.10025 -0.1755 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85728 1.07528 -0.2027 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.85314 1.07017 -0.2028 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.85320 1.07017 -0.2027 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.81319 1.05560 -0.2296 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.76016 1.03672 -0.2668 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-77 Table 2.81 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91476 1.10682 -0.1735 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90174 1.10025 -0.1804 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85081 1.07528 -0.2087 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84672 1.07017 -0.2088 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84680 1.07017 -0.2087 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.80571 1.05560 -0.2367 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.75095 1.03672 -0.2757 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-78 Table 2.82 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93801 1.10682 -0.1525 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92582 1.10025 -0.1585 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.88022 1.07528 -0.1814 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.87594 1.07017 -0.1815 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.87594 1.07017 -0.1815 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.84032 1.05560 -0.2039 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.79317 1.03672 -0.2349 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-79 Table 2.83 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91208 1.10682 -0.1759 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89881 1.10025 -0.1831 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84670 1.07528 -0.2126 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84262 1.07017 -0.2126 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84271 1.07017 -0.2125 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79993 1.05560 -0.2422 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.74258 1.03672 -0.2837 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-80 Table 2.84 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91013 1.10682 -0.1777 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89680 1.10025 -0.1849 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84427 1.07528 -0.2148 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84021 1.07017 -0.2149 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84030 1.07017 -0.2148 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79706 1.05560 -0.2449 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.73905 1.03672 -0.2871 80% Void Table 2.85 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.07017 1.07528 -0.0047 1.05560 1.07017 -0.0136 1.07528 1.10682 -0.0285
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-81 Table 2.86 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91342 1.08896 -0.1612 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89981 1.08200 -0.1684 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84976 1.05821 -0.1970 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84573 1.05327 -0.1970 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84580 1.05327 -0.1970 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.80602 1.03972 -0.2248 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.75200 1.02116 -0.2636 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-82 Table 2.87 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91303 1.08896 -0.1616 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89954 1.08200 -0.1686 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84963 1.05821 -0.1971 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84561 1.05327 -0.1972 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84566 1.05327 -0.1971 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.80545 1.03972 -0.2253 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.75061 1.02116 -0.2649 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-83 Table 2.88 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90802 1.08896 -0.1662 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89454 1.08200 -0.1732 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84359 1.05821 -0.2028 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.83961 1.05327 -0.2029 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.83969 1.05327 -0.2028 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79837 1.03972 -0.2321 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.74173 1.02116 -0.2736 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-84 Table 2.89 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92963 1.08896 -0.1463 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91695 1.08200 -0.1525 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87134 1.05821 -0.1766 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.86719 1.05327 -0.1767 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.86719 1.05327 -0.1767 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.83156 1.03972 -0.2002 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.78299 1.02116 -0.2332 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-85 Table 2.90 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90571 1.08896 -0.1683 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89200 1.08200 -0.1756 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.83998 1.05821 -0.2062 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.83601 1.05327 -0.2063 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.83609 1.05327 -0.2062 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79314 1.03972 -0.2372 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.73388 1.02116 -0.2813 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-86 Table 2.91 Lattice [ A11T-4497L-13G85 ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90388 1.08896 -0.1700 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89011 1.08200 -0.1774 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.83767 1.05821 -0.2084 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.83372 1.05327 -0.2084 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.83380 1.05327 -0.2084 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79037 1.03972 -0.2398 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.73041 1.02116 -0.2847 80% Void Table 2.92 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.05327 1.05821 -0.0047 1.03972 1.05327 -0.0129 1.05821 1.08896 -0.0282
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-87 Table 2.93 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92670 1.10289 -0.1598 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91388 1.09694 -0.1669 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86789 1.07875 -0.1955 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.86386 1.07383 -0.1955 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.86393 1.07383 -0.1955 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.82583 1.06337 -0.2234 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.77301 1.04873 -0.2629 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-88 Table 2.94 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92629 1.10289 -0.1601 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91359 1.09694 -0.1671 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86774 1.07875 -0.1956 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.86372 1.07383 -0.1957 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.86378 1.07383 -0.1956 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.82523 1.06337 -0.2240 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.77155 1.04873 -0.2643 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-89 Table 2.95 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92116 1.10289 -0.1648 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90847 1.09694 -0.1718 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86148 1.07875 -0.2014 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.85751 1.07383 -0.2014 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.85759 1.07383 -0.2014 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.81784 1.06337 -0.2309 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.76221 1.04873 -0.2732 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-90 Table 2.96 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.94301 1.10289 -0.1450 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.93114 1.09694 -0.1512 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.88976 1.07875 -0.1752 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.88561 1.07383 -0.1753 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.88561 1.07383 -0.1753 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.85186 1.06337 -0.1989 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.80486 1.04873 -0.2325 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-91 Table 2.97 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91891 1.10289 -0.1668 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90599 1.09694 -0.1741 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85794 1.07875 -0.2047 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.85398 1.07383 -0.2047 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.85406 1.07383 -0.2047 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.81267 1.06337 -0.2358 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.75435 1.04873 -0.2807 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-92 Table 2.98 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91707 1.10289 -0.1685 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90408 1.09694 -0.1758 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85560 1.07875 -0.2069 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.85165 1.07383 -0.2069 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.85173 1.07383 -0.2068 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.80983 1.06337 -0.2384 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.75077 1.04873 -0.2841 80% Void Table 2.99 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.07383 1.07875 -0.0046 1.06337 1.07383 -0.0097 1.07875 1.10289 -0.0219
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-93 Table 2.100 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.94396 1.12760 -0.1629 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.93107 1.12127 -0.1696 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87971 1.09465 -0.1964 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.87557 1.08960 -0.1964 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.87564 1.08960 -0.1964 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.83346 1.07180 -0.2224 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.77974 1.04997 -0.2574 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-94 Table 2.101 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.94348 1.12760 -0.1633 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.93071 1.12127 -0.1699 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87945 1.09465 -0.1966 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.87531 1.08960 -0.1967 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.87537 1.08960 -0.1966 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.83274 1.07180 -0.2230 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.77820 1.04997 -0.2588 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-95 Table 2.102 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93795 1.12760 -0.1682 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92519 1.12127 -0.1749 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87284 1.09465 -0.2026 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.86876 1.08960 -0.2027 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.86884 1.08960 -0.2026 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.82513 1.07180 -0.2301 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.76890 1.04997 -0.2677 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-96 Table 2.103 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.96124 1.12760 -0.1475 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.94930 1.12127 -0.1534 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.90220 1.09465 -0.1758 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.89794 1.08960 -0.1759 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.89794 1.08960 -0.1759 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.85961 1.07180 -0.1980 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.81069 1.04997 -0.2279 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-97 Table 2.104 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93535 1.12760 -0.1705 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92232 1.12127 -0.1774 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86871 1.09465 -0.2064 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.86464 1.08960 -0.2065 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.86473 1.08960 -0.2064 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.81930 1.07180 -0.2356 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.76049 1.04997 -0.2757 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-98 Table 2.105 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93340 1.12760 -0.1722 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92031 1.12127 -0.1792 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86630 1.09465 -0.2086 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=979° F 0.86225 1.08960 -0.2087 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=979° F 0.86233 1.08960 -0.2086 0% Void Hot Operating40 TModerator=550° F TFuel=979° F 0.81645 1.07180 -0.2382 40% Void Hot Operating 80 TModerator=550° F TFuel=979° F 0.75701 1.04997 -0.2790 80% Void Table 2.106 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.08960 1.09465 -0.0046 1.07180 1.08960 -0.0163 1.09465 1.12760 -0.0292
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-99 Table 2.107 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91716 1.10327 -0.1687 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90384 1.09648 -0.1757 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85287 1.07015 -0.2030 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84872 1.06503 -0.2031 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84879 1.06503 -0.2030 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.80869 1.04956 -0.2295 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.75622 1.02975 -0.2656 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-100 Table 2.108 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91674 1.10327 -0.1691 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90354 1.09648 -0.1760 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85268 1.07015 -0.2032 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84853 1.06503 -0.2033 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84859 1.06503 -0.2032 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.80805 1.04956 -0.2301 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.75478 1.02975 -0.2670 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-101 Table 2.109 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91131 1.10327 -0.1740 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89813 1.09648 -0.1809 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84625 1.07015 -0.2092 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84216 1.06503 -0.2093 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84224 1.06503 -0.2092 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.80065 1.04956 -0.2372 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.74568 1.02975 -0.2759 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-102 Table 2.110 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.93450 1.10327 -0.1530 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.92215 1.09648 -0.1590 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.87553 1.07015 -0.1819 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.87125 1.06503 -0.1820 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.87125 1.06503 -0.1820 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.83505 1.04956 -0.2044 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.78755 1.02975 -0.2352 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-103 Table 2.111 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90862 1.10327 -0.1764 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89518 1.09648 -0.1836 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84212 1.07015 -0.2131 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.83804 1.06503 -0.2131 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.83813 1.06503 -0.2130 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79486 1.04956 -0.2427 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.73731 1.02975 -0.2840 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-104 Table 2.112 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90667 1.10327 -0.1782 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89318 1.09648 -0.1854 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.83971 1.07015 -0.2153 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.83565 1.06503 -0.2154 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.83573 1.06503 -0.2153 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79200 1.04956 -0.2454 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.73381 1.02975 -0.2874 80% Void Table 2.113 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.06503 1.07015 -0.0048 1.04956 1.06503 -0.0145 1.07015 1.10327 -0.0300
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-105 Table 2.114 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91183 1.08855 -0.1623 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89811 1.08145 -0.1695 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84728 1.05634 -0.1979 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84324 1.05139 -0.1980 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84330 1.05139 -0.1979 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.80306 1.03692 -0.2255 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.74877 1.01740 -0.2640 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-106 Table 2.115 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91145 1.08855 -0.1627 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89785 1.08145 -0.1698 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84716 1.05634 -0.1980 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.84312 1.05139 -0.1981 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.84318 1.05139 -0.1980 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.80250 1.03692 -0.2261 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.74741 1.01740 -0.2654 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-107 Table 2.116 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90637 1.08855 -0.1674 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89278 1.08145 -0.1745 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.84106 1.05634 -0.2038 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.83707 1.05139 -0.2038 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.83715 1.05139 -0.2038 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79538 1.03692 -0.2329 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.73852 1.01740 -0.2741 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-108 Table 2.117 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92809 1.08855 -0.1474 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91531 1.08145 -0.1536 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86887 1.05634 -0.1775 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.86471 1.05139 -0.1776 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.86471 1.05139 -0.1776 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.82854 1.03692 -0.2010 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.77960 1.01740 -0.2337 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-109 Table 2.118 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90406 1.08855 -0.1695 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.89024 1.08145 -0.1768 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.83743 1.05634 -0.2072 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.83346 1.05139 -0.2073 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.83354 1.05139 -0.2072 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.79014 1.03692 -0.2380 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.73066 1.01740 -0.2818 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-110 Table 2.119 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.90221 1.08855 -0.1712 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.88834 1.08145 -0.1786 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.83512 1.05634 -0.2094 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.83116 1.05139 -0.2095 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.83124 1.05139 -0.2094 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.78736 1.03692 -0.2407 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.72720 1.01740 -0.2852 80% Void Table 2.120 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.05139 1.05634 -0.0047 1.03692 1.05139 -0.0138 1.05634 1.08855 -0.0296
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-111 Table 2.121 Lattice [ ] Control Blade Worths at BOL for Control Blade Type GE Original Equipment kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92796 1.10503 -0.1602 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91519 1.09915 -0.1674 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86936 1.08101 -0.1958 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.86533 1.07609 -0.1959 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.86540 1.07609 -0.1958 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.82738 1.06566 -0.2236 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.77460 1.05106 -0.2630 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-112 Table 2.122 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Duralife 160 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92755 1.10503 -0.1606 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.91491 1.09915 -0.1676 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86922 1.08101 -0.1959 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.86519 1.07609 -0.1960 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.86525 1.07609 -0.1959 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.82678 1.06566 -0.2242 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.77314 1.05106 -0.2644 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-113 Table 2.123 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92237 1.10503 -0.1653 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90972 1.09915 -0.1723 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.86290 1.08101 -0.2018 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.85893 1.07609 -0.2018 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.85901 1.07609 -0.2017 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.81933 1.06566 -0.2311 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.76373 1.05106 -0.2734 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-114 Table 2.124 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR82M-1 HF TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.94434 1.10503 -0.1454 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.93253 1.09915 -0.1516 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.89131 1.08101 -0.1755 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.88716 1.07609 -0.1756 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.88716 1.07609 -0.1756 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.85348 1.06566 -0.1991 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.80650 1.05106 -0.2327 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-115 Table 2.125 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 TIP kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.92012 1.10503 -0.1673 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90725 1.09915 -0.1746 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85935 1.08101 -0.2051 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.85539 1.07609 -0.2051 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.85547 1.07609 -0.2050 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.81414 1.06566 -0.2360 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.75586 1.05106 -0.2809 80% Void
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-116 Table 2.126 Lattice [ ] Control Blade Worths at BOL for Control Blade Type Westinghouse-ABB CR99 kControlled kUncontrolled Blade Worth (k/k)
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| Cold TModerator=68° F TFuel=68° F 0.91827 1.10503 -0.1690 0% Void, No xenon Intermediate TModerator=200° F TFuel=200° F 0.90533 1.09915 -0.1763 0% Void, No xenon Hot Standby TModerator=550° F TFuel=550° F 0.85700 1.08101 -0.2072 0% Void, No xenon Hot OperatingNoXe TModerator=550° F TFuel=1017° F 0.85305 1.07609 -0.2073 0% Void, No xenon Hot Operating0 TModerator=550° F TFuel=1017° F 0.85313 1.07609 -0.2072 0% Void Hot Operating40 TModerator=550° F TFuel=1017° F 0.81129 1.06566 -0.2387 40% Void Hot Operating 80 TModerator=550° F TFuel=1017° F 0.75226 1.05106 -0.2843 80% Void Table 2.127 Lattice [ ] Kinetics Parameters at BOL Kinetics Parameter k k (k/k) 1.07609 1.08101 -0.0046 1.06566 1.07609 -0.0097 1.08101 1.10503 -0.0217
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-117 Figure 2.1 Assembly Type [ ]
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-118 Figure 2.2 Assembly Type [ ]
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-119 Figure 2.3 Assembly Type [ ]
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-120 Figure 2.4 [ ] Fuel Rod Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-121 Figure 2.5 [ ] Fuel Rod Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-122 Figure 2.6 [ ] Fuel Rod Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-123 Figure 2.7 Fuel Rod Axial Description
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-124 Figure 2.7 Fuel Rod Axial Description (Continued)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 2-125 Figure 2.7 Fuel Rod Axial Description (Continued)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page 3-1
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| ==3.0 REFERENCES==
| |
| : 1. FS1-0031299 Revision 4.0, Brunswick Unit 1 Cycle 23 Reload BRK1-23 ATRIUM 11 Specific Fuel Assembly Mechanical Data for Core Engineering, August 2019.
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| : 2. ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
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| : 3. 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.
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| : 4. ANP-3672P, Revision 0, Brunswick Nuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUM 11 Fuel, August 2018.
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| : 5. ANP-3671P, Revision 0, Brunswick Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for ATRIUM 11 Fuel, December 2018.
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| : 6. Certificate of Compliance No. 9372 Revision No. 1 For the Model No. TN-B1 Transportation Package, March 27, 2018.
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-1 Appendix A Enriched Lattice Hot Uncontrolled Reactivity and LPF Plots The results in this appendix are based on hot operating and equilibrium xenon conditions.
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-2 1.23 1.18 0%
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| 1.13 40%
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| 80%
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| Hot Uncontrolled k 1.08 1.03 0.98 0.93 0.88 0.83 0.78 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.1 [ ] Hot Uncontrolled k 1.50 0%
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| Hot Uncontrolled Local Peaking Factor 1.45 1.40 40%
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| 80%
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| 1.35 1.30 1.25 1.20 1.15 1.10 1.05 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.2 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-3 1.23 1.18 0%
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| 1.13 40%
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| 80%
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| Hot Uncontrolled k 1.08 1.03 0.98 0.93 0.88 0.83 0.78 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.3 [ ] Hot Uncontrolled k 1.40 0%
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| Hot Uncontrolled Local Peaking Factor 1.35 40%
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| 1.30 80%
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| 1.25 1.20 1.15 1.10 1.05 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.4 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-4 1.24 1.19 0%
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| 1.14 40%
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| 80%
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| Hot Uncontrolled k 1.09 1.04 0.99 0.94 0.89 0.84 0.79 0.74 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.5 [ ] Hot Uncontrolled k 1.49 0%
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| Hot Uncontrolled Local Peaking Factor 1.44 1.39 40%
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| 80%
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| 1.34 1.29 1.24 1.19 1.14 1.09 1.04 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.6 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-5 1.23 1.18 0%
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| 1.13 40%
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| 80%
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| Hot Uncontrolled k 1.08 1.03 0.98 0.93 0.88 0.83 0.78 0.73 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.7 [ ] Hot Uncontrolled k 1.40 0%
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| Hot Uncontrolled Local Peaking Factor 1.35 40%
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| 1.30 80%
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| 1.25 1.20 1.15 1.10 1.05 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.8 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-6 1.31 0%
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| 1.21 40%
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| 80%
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| Hot Uncontrolled k 1.11 1.01 0.91 0.81 0.71 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.9 [ ] Hot Uncontrolled k 1.34 0%
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| Hot Uncontrolled Local Peaking Factor 1.29 40%
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| 80%
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| 1.24 1.19 1.14 1.09 1.04 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.10 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-7 1.30 0%
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| 1.20 40%
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| 80%
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| Hot Uncontrolled k 1.10 1.00 0.90 0.80 0.70 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.11 [ ] Hot Uncontrolled k 1.35 0%
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| Hot Uncontrolled Local Peaking Factor 1.30 40%
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| 80%
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| 1.25 1.20 1.15 1.10 1.05 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.12 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-8 1.30 0%
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| 1.20 40%
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| 80%
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| Hot Uncontrolled k 1.10 1.00 0.90 0.80 0.70 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.13 [ ] Hot Uncontrolled k 1.34 0%
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| Hot Uncontrolled Local Peaking Factor 1.29 40%
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| 80%
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| 1.24 1.19 1.14 1.09 1.04 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.14 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-9 1.23 1.18 0%
| |
| 1.13 40%
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| 80%
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| Hot Uncontrolled k 1.08 1.03 0.98 0.93 0.88 0.83 0.78 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.15 [ ] Hot Uncontrolled k 1.54 0%
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| Hot Uncontrolled Local Peaking Factor 1.49 1.44 40%
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| 1.39 80%
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| 1.34 1.29 1.24 1.19 1.14 1.09 1.04 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.16 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-10 1.23 1.18 0%
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| 1.13 40%
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| 80%
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| Hot Uncontrolled k 1.08 1.03 0.98 0.93 0.88 0.83 0.78 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.17 [ ] Hot Uncontrolled k 1.49 0%
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| Hot Uncontrolled Local Peaking Factor 1.44 1.39 40%
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| 80%
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| 1.34 1.29 1.24 1.19 1.14 1.09 1.04 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.18 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-11 1.25 1.20 0%
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| 1.15 40%
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| 80%
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| Hot Uncontrolled k 1.10 1.05 1.00 0.95 0.90 0.85 0.80 0.75 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.19 [ ] Hot Uncontrolled k 1.54 0%
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| Hot Uncontrolled Local Peaking Factor 1.49 1.44 40%
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| 1.39 80%
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| 1.34 1.29 1.24 1.19 1.14 1.09 1.04 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.20 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-12 1.24 1.19 0%
| |
| 1.14 40%
| |
| 80%
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| Hot Uncontrolled k 1.09 1.04 0.99 0.94 0.89 0.84 0.79 0.74 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.21 [ ] Hot Uncontrolled k 1.53 0%
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| Hot Uncontrolled Local Peaking Factor 1.48 1.43 40%
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| 1.38 80%
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| 1.33 1.28 1.23 1.18 1.13 1.08 1.03 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.22 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-13 1.22 1.17 0%
| |
| 1.12 40%
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| 80%
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| Hot Uncontrolled k 1.07 1.02 0.97 0.92 0.87 0.82 0.77 0.72 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.23 [ ] Hot Uncontrolled k 1.48 0%
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| Hot Uncontrolled Local Peaking Factor 1.43 1.38 40%
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| 80%
| |
| 1.33 1.28 1.23 1.18 1.13 1.08 1.03 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.24 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-14 1.30 0%
| |
| 1.20 40%
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| 80%
| |
| Hot Uncontrolled k 1.10 1.00 0.90 0.80 0.70 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.25 [ ] Hot Uncontrolled k 1.44 0%
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| Hot Uncontrolled Local Peaking Factor 1.39 40%
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| 1.34 80%
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| 1.29 1.24 1.19 1.14 1.09 1.04 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.26 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-15 1.30 0%
| |
| 1.20 40%
| |
| 80%
| |
| Hot Uncontrolled k 1.10 1.00 0.90 0.80 0.70 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.27 [ ] Hot Uncontrolled k 1.44 0%
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| Hot Uncontrolled Local Peaking Factor 1.39 40%
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| 1.34 80%
| |
| 1.29 1.24 1.19 1.14 1.09 1.04 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.28 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-16 1.24 1.19 0%
| |
| 1.14 40%
| |
| 80%
| |
| Hot Uncontrolled k 1.09 1.04 0.99 0.94 0.89 0.84 0.79 0.74 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.29 [ ] Hot Uncontrolled k 1.54 0%
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| Hot Uncontrolled Local Peaking Factor 1.49 1.44 40%
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| 1.39 80%
| |
| 1.34 1.29 1.24 1.19 1.14 1.09 1.04 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.30 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-17 1.22 1.17 0%
| |
| 1.12 40%
| |
| 80%
| |
| Hot Uncontrolled k 1.07 1.02 0.97 0.92 0.87 0.82 0.77 0.72 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.31 [ ] Hot Uncontrolled k 1.48 0%
| |
| Hot Uncontrolled Local Peaking Factor 1.43 1.38 40%
| |
| 80%
| |
| 1.33 1.28 1.23 1.18 1.13 1.08 1.03 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.32 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-18 1.20 1.15 0%
| |
| 1.10 40%
| |
| 80%
| |
| Hot Uncontrolled k 1.05 1.00 0.95 0.90 0.85 0.80 0.75 0.70 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.33 [ ] Hot Uncontrolled k 1.44 0%
| |
| Hot Uncontrolled Local Peaking Factor 1.39 40%
| |
| 1.34 80%
| |
| 1.29 1.24 1.19 1.14 1.09 1.04 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.34 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page A-19 1.30 0%
| |
| 1.20 40%
| |
| 80%
| |
| Hot Uncontrolled k 1.10 1.00 0.90 0.80 0.70 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
| |
| Figure A.35 [ ] Hot Uncontrolled k 1.44 0%
| |
| Hot Uncontrolled Local Peaking Factor 1.39 40%
| |
| 1.34 80%
| |
| 1.29 1.24 1.19 1.14 1.09 1.04 0 10 20 30 40 50 60 70 Lattice Exposure (GWd/MTU)
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| Figure A.36 [ ] Hot Uncontrolled LPF
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-1 Appendix B Enriched Lattice Hot Uncontrolled Reactivity and LPF Tables The results in this appendix are based on hot operating and equilibrium xenon conditions.
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-2 Table B.1 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.05445 1.03844 1.02081 100. 1.03179 1.01754 1.00234 500. 1.03170 1.01802 1.00330 1000. 1.03581 1.02224 1.00735 1500. 1.04130 1.02751 1.01206 2000. 1.04731 1.03312 1.01687 2500. 1.05362 1.03884 1.02161 3000. 1.06020 1.04465 1.02626 3500. 1.06704 1.05053 1.03083 4000. 1.07407 1.05648 1.03534 4500. 1.08104 1.06239 1.03977 5000. 1.08757 1.06810 1.04408 5500. 1.09343 1.07337 1.04818 6000. 1.09861 1.07813 1.05199 6500. 1.10323 1.08241 1.05546 7000. 1.10738 1.08631 1.05861 7500. 1.11116 1.08987 1.06151 8000. 1.11472 1.09318 1.06420 8500. 1.11816 1.09629 1.06673 9000. 1.12158 1.09929 1.06912 9500. 1.12504 1.10223 1.07140 10000. 1.12860 1.10517 1.07359 10500. 1.13233 1.10818 1.07573 11000. 1.13625 1.11128 1.07784 11500. 1.14040 1.11449 1.07997 12000. 1.14477 1.11781 1.08211 12500. 1.14935 1.12123 1.08427 13000. 1.15410 1.12472 1.08642 13500. 1.15891 1.12820 1.08852 14000. 1.16366 1.13163 1.09055 14500. 1.16821 1.13490 1.09245 15000. 1.17233 1.13795 1.09420 15500. 1.17588 1.14068 1.09577 16000. 1.17866 1.14301 1.09714 16500. 1.18057 1.14486 1.09829 17000. 1.18156 1.14617 1.09919 17500. 1.18165 1.14691 1.09983 18000. 1.18084 1.14706 1.10020 18500. 1.17922 1.14662 1.10027 19000. 1.17693 1.14563 1.10003 19500. 1.17410 1.14410 1.09949 20000. 1.17084 1.14208 1.09863 20500. 1.16727 1.13964 1.09749 21000. 1.16344 1.13685 1.09605 21500. 1.15942 1.13377 1.09435 22000. 1.15527 1.13047 1.09238 22500. 1.15102 1.12700 1.09018 23000. 1.14660 1.12339 1.08776 23500. 1.14217 1.11969 1.08515 24000. 1.13775 1.11590 1.08239 24500. 1.13332 1.11207 1.07949 25000. 1.12890 1.10821 1.07649 25500. 1.12452 1.10428 1.07340 26000. 1.12014 1.10035 1.07025 26500. 1.11575 1.09643 1.06704 27000. 1.11137 1.09250 1.06379 27500. 1.10699 1.08857 1.06052 28000. 1.10261 1.08472 1.05723 28500. 1.09823 1.08087 1.05393 29000. 1.09385 1.07703 1.05062 29500. 1.08947 1.07318 1.04732 30000. 1.08509 1.06933 1.04402 32500. 1.06320 1.05034 1.02764 35000. 1.04132 1.03162 1.01174 37500. 1.01947 1.01316 0.99626 40000. 0.99768 0.99499 0.98121 42500. 0.97602 0.97714 0.96662 45000. 0.95454 0.95964 0.95248 47500. 0.93336 0.94254 0.93884 50000. 0.91257 0.92587 0.92569 52500. 0.89229 0.90969 0.91307 55000. 0.87266 0.89406 0.90097 57500. 0.85380 0.87902 0.88941 60000. 0.83584 0.86463 0.87840 62500. 0.81892 0.85093 0.86794 65000. 0.80312 0.83796 0.85803 67500. 0.78855 0.82577 0.84866 70000. 0.77524 0.81436 0.83985
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-3 Table B.2 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.429 1.425 1.398 100. 1.427 1.423 1.394 500. 1.418 1.417 1.394 1000. 1.408 1.410 1.395 1500. 1.395 1.400 1.394 2000. 1.382 1.390 1.390 2500. 1.367 1.378 1.385 3000. 1.352 1.366 1.379 3500. 1.336 1.354 1.372 4000. 1.320 1.341 1.365 4500. 1.305 1.328 1.357 5000. 1.294 1.315 1.349 5500. 1.284 1.303 1.340 6000. 1.275 1.291 1.332 6500. 1.266 1.280 1.324 7000. 1.258 1.269 1.316 7500. 1.251 1.258 1.308 8000. 1.244 1.250 1.300 8500. 1.236 1.244 1.292 9000. 1.229 1.238 1.284 9500. 1.222 1.232 1.276 10000. 1.215 1.226 1.269 10500. 1.208 1.220 1.261 11000. 1.201 1.214 1.254 11500. 1.194 1.209 1.246 12000. 1.186 1.203 1.239 12500. 1.179 1.197 1.231 13000. 1.172 1.191 1.224 13500. 1.164 1.185 1.216 14000. 1.156 1.179 1.209 14500. 1.147 1.172 1.202 15000. 1.139 1.165 1.194 15500. 1.130 1.159 1.189 16000. 1.122 1.152 1.185 16500. 1.114 1.145 1.180 17000. 1.107 1.139 1.175 17500. 1.101 1.132 1.170 18000. 1.096 1.127 1.166 18500. 1.094 1.121 1.161 19000. 1.094 1.117 1.157 19500. 1.094 1.112 1.153 20000. 1.093 1.109 1.149 20500. 1.092 1.105 1.145 21000. 1.091 1.102 1.142 21500. 1.090 1.099 1.139 22000. 1.089 1.097 1.136 22500. 1.089 1.095 1.133 23000. 1.088 1.093 1.131 23500. 1.088 1.091 1.129 24000. 1.087 1.089 1.127 24500. 1.087 1.087 1.125 25000. 1.086 1.085 1.123 25500. 1.085 1.084 1.121 26000. 1.085 1.083 1.120 26500. 1.084 1.083 1.118 27000. 1.084 1.082 1.117 27500. 1.083 1.081 1.115 28000. 1.082 1.080 1.114 28500. 1.081 1.080 1.113 29000. 1.081 1.079 1.111 29500. 1.080 1.079 1.110 30000. 1.079 1.078 1.109 32500. 1.075 1.075 1.103 35000. 1.072 1.072 1.100 37500. 1.067 1.069 1.098 40000. 1.064 1.066 1.097 42500. 1.060 1.064 1.099 45000. 1.057 1.061 1.105 47500. 1.054 1.059 1.112 50000. 1.051 1.056 1.120 52500. 1.048 1.054 1.129 55000. 1.050 1.053 1.138 57500. 1.050 1.051 1.149 60000. 1.050 1.055 1.159 62500. 1.048 1.069 1.170 65000. 1.045 1.084 1.181 67500. 1.063 1.099 1.191 70000. 1.081 1.113 1.202
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-4 Table B.3 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.11537 1.09453 1.07061 100. 1.08955 1.07059 1.04923 500. 1.08637 1.06816 1.04758 1000. 1.08653 1.06878 1.04851 1500. 1.08784 1.07035 1.05011 2000. 1.08946 1.07213 1.05178 2500. 1.09116 1.07394 1.05337 3000. 1.09292 1.07571 1.05486 3500. 1.09474 1.07748 1.05628 4000. 1.09667 1.07928 1.05766 4500. 1.09871 1.08112 1.05902 5000. 1.10085 1.08303 1.06037 5500. 1.10309 1.08499 1.06173 6000. 1.10544 1.08701 1.06310 6500. 1.10790 1.08910 1.06450 7000. 1.11047 1.09128 1.06595 7500. 1.11318 1.09354 1.06746 8000. 1.11603 1.09588 1.06904 8500. 1.11902 1.09831 1.07067 9000. 1.12216 1.10083 1.07236 9500. 1.12545 1.10345 1.07410 10000. 1.12890 1.10619 1.07588 10500. 1.13255 1.10905 1.07772 11000. 1.13643 1.11206 1.07963 11500. 1.14054 1.11521 1.08159 12000. 1.14489 1.11850 1.08362 12500. 1.14945 1.12189 1.08569 13000. 1.15417 1.12535 1.08777 13500. 1.15895 1.12882 1.08983 14000. 1.16367 1.13221 1.09180 14500. 1.16819 1.13547 1.09366 15000. 1.17229 1.13849 1.09537 15500. 1.17583 1.14121 1.09690 16000. 1.17862 1.14354 1.09823 16500. 1.18057 1.14537 1.09934 17000. 1.18162 1.14669 1.10021 17500. 1.18178 1.14744 1.10083 18000. 1.18108 1.14761 1.10118 18500. 1.17958 1.14720 1.10123 19000. 1.17740 1.14624 1.10097 19500. 1.17467 1.14476 1.10042 20000. 1.17150 1.14279 1.09956 20500. 1.16800 1.14040 1.09841 21000. 1.16423 1.13765 1.09698 21500. 1.16027 1.13461 1.09527 22000. 1.15615 1.13135 1.09332 22500. 1.15192 1.12790 1.09112 23000. 1.14749 1.12432 1.08871 23500. 1.14307 1.12063 1.08612 24000. 1.13864 1.11686 1.08336 24500. 1.13422 1.11303 1.08047 25000. 1.12979 1.10917 1.07747 25500. 1.12540 1.10524 1.07439 26000. 1.12100 1.10130 1.07124 26500. 1.11661 1.09737 1.06803 27000. 1.11221 1.09343 1.06478 27500. 1.10782 1.08950 1.06150 28000. 1.10343 1.08564 1.05821 28500. 1.09904 1.08178 1.05490 29000. 1.09464 1.07792 1.05159 29500. 1.09025 1.07406 1.04828 30000. 1.08586 1.07020 1.04497 30500. 1.08147 1.06639 1.04167 32500. 1.06391 1.05115 1.02852 35000. 1.04197 1.03237 1.01257 37500. 1.02006 1.01386 0.99705 40000. 0.99821 0.99564 0.98196 42500. 0.97649 0.97774 0.96732 45000. 0.95497 0.96020 0.95315 47500. 0.93374 0.94305 0.93947 50000. 0.91291 0.92635 0.92630 52500. 0.89260 0.91013 0.91364 55000. 0.87294 0.89447 0.90152 57500. 0.85406 0.87941 0.88995 60000. 0.83610 0.86500 0.87892 62500. 0.81917 0.85129 0.86844 65000. 0.80338 0.83832 0.85852 67500. 0.78882 0.82612 0.84914 70000. 0.77553 0.81472 0.84032
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-5 Table B.4 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.354 1.358 1.357 100. 1.354 1.359 1.355 500. 1.350 1.357 1.353 1000. 1.345 1.354 1.357 1500. 1.339 1.350 1.358 2000. 1.332 1.345 1.358 2500. 1.324 1.338 1.356 3000. 1.315 1.332 1.353 3500. 1.308 1.325 1.349 4000. 1.301 1.317 1.345 4500. 1.294 1.309 1.340 5000. 1.287 1.301 1.335 5500. 1.280 1.293 1.330 6000. 1.273 1.284 1.324 6500. 1.266 1.276 1.317 7000. 1.259 1.267 1.311 7500. 1.252 1.258 1.304 8000. 1.245 1.250 1.297 8500. 1.238 1.244 1.290 9000. 1.231 1.239 1.283 9500. 1.224 1.233 1.276 10000. 1.217 1.227 1.269 10500. 1.210 1.222 1.262 11000. 1.203 1.216 1.254 11500. 1.196 1.210 1.247 12000. 1.189 1.204 1.240 12500. 1.181 1.199 1.232 13000. 1.174 1.193 1.225 13500. 1.166 1.187 1.218 14000. 1.158 1.180 1.210 14500. 1.149 1.174 1.203 15000. 1.141 1.167 1.195 15500. 1.133 1.160 1.190 16000. 1.124 1.153 1.185 16500. 1.116 1.146 1.180 17000. 1.109 1.140 1.175 17500. 1.103 1.134 1.171 18000. 1.097 1.128 1.166 18500. 1.094 1.123 1.161 19000. 1.094 1.118 1.157 19500. 1.094 1.113 1.153 20000. 1.093 1.110 1.149 20500. 1.092 1.106 1.145 21000. 1.091 1.103 1.142 21500. 1.091 1.100 1.139 22000. 1.091 1.098 1.136 22500. 1.091 1.095 1.133 23000. 1.090 1.093 1.131 23500. 1.090 1.091 1.129 24000. 1.089 1.089 1.127 24500. 1.089 1.087 1.125 25000. 1.088 1.086 1.123 25500. 1.087 1.085 1.121 26000. 1.087 1.084 1.120 26500. 1.086 1.084 1.118 27000. 1.086 1.083 1.117 27500. 1.085 1.082 1.115 28000. 1.084 1.081 1.114 28500. 1.083 1.081 1.113 29000. 1.083 1.080 1.111 29500. 1.082 1.080 1.110 30000. 1.081 1.079 1.109 30500. 1.080 1.078 1.108 32500. 1.078 1.076 1.103 35000. 1.074 1.073 1.100 37500. 1.070 1.071 1.098 40000. 1.066 1.068 1.098 42500. 1.061 1.065 1.099 45000. 1.057 1.062 1.105 47500. 1.054 1.059 1.112 50000. 1.051 1.056 1.120 52500. 1.048 1.054 1.129 55000. 1.050 1.052 1.138 57500. 1.051 1.051 1.148 60000. 1.051 1.055 1.159 62500. 1.049 1.069 1.170 65000. 1.046 1.084 1.180 67500. 1.063 1.098 1.191 70000. 1.081 1.113 1.202
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-6 Table B.5 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.08383 1.06735 1.04750 100. 1.05812 1.04337 1.02595 500. 1.05532 1.04136 1.02475 1000. 1.05604 1.04263 1.02640 1500. 1.05808 1.04501 1.02886 2000. 1.06050 1.04769 1.03148 2500. 1.06308 1.05045 1.03405 3000. 1.06578 1.05325 1.03657 3500. 1.06864 1.05611 1.03904 4000. 1.07168 1.05907 1.04151 4500. 1.07490 1.06213 1.04398 5000. 1.07829 1.06529 1.04648 5500. 1.08183 1.06856 1.04899 6000. 1.08551 1.07192 1.05154 6500. 1.08936 1.07540 1.05414 7000. 1.09340 1.07900 1.05682 7500. 1.09763 1.08273 1.05959 8000. 1.10207 1.08658 1.06243 8500. 1.10671 1.09057 1.06536 9000. 1.11156 1.09469 1.06836 9500. 1.11664 1.09897 1.07144 10000. 1.12199 1.10343 1.07461 10500. 1.12767 1.10810 1.07787 11000. 1.13370 1.11299 1.08125 11500. 1.14011 1.11811 1.08473 12000. 1.14687 1.12342 1.08829 12500. 1.15392 1.12890 1.09189 13000. 1.16113 1.13445 1.09548 13500. 1.16822 1.13996 1.09901 14000. 1.17490 1.14527 1.10240 14500. 1.18081 1.15023 1.10562 15000. 1.18575 1.15466 1.10860 15500. 1.18948 1.15840 1.11131 16000. 1.19190 1.16137 1.11368 16500. 1.19303 1.16349 1.11568 17000. 1.19302 1.16471 1.11726 17500. 1.19204 1.16507 1.11841 18000. 1.19028 1.16463 1.11909 18500. 1.18788 1.16347 1.11932 19000. 1.18499 1.16169 1.11908 19500. 1.18171 1.15938 1.11840 20000. 1.17809 1.15666 1.11731 20500. 1.17420 1.15360 1.11582 21000. 1.17008 1.15029 1.11397 21500. 1.16578 1.14677 1.11179 22000. 1.16137 1.14307 1.10933 22500. 1.15676 1.13923 1.10664 23000. 1.15208 1.13529 1.10374 23500. 1.14740 1.13128 1.10069 24000. 1.14272 1.12721 1.09751 24500. 1.13804 1.12301 1.09423 25000. 1.13336 1.11880 1.09087 25500. 1.12869 1.11464 1.08744 26000. 1.12403 1.11047 1.08397 26500. 1.11936 1.10631 1.08047 27000. 1.11470 1.10214 1.07694 27500. 1.11003 1.09798 1.07341 28000. 1.10532 1.09386 1.06986 30000. 1.08650 1.07740 1.05555 32500. 1.06275 1.05692 1.03813 35000. 1.03877 1.03653 1.02104 37500. 1.01459 1.01624 1.00429 40000. 0.99026 0.99608 0.98788 42500. 0.96586 0.97610 0.97185 45000. 0.94149 0.95636 0.95622 47500. 0.91731 0.93691 0.94102 50000. 0.89349 0.91782 0.92629 52500. 0.87022 0.89920 0.91206 55000. 0.84771 0.88114 0.89836 57500. 0.82620 0.86375 0.88521 60000. 0.80590 0.84711 0.87264 62500. 0.78702 0.83131 0.86066 65000. 0.76971 0.81645 0.84930 67500. 0.75409 0.80258 0.83858 70000. 0.74021 0.78976 0.82849
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-7 Table B.6 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.420 1.423 1.408 100. 1.419 1.422 1.408 500. 1.412 1.417 1.406 1000. 1.404 1.411 1.403 1500. 1.394 1.403 1.399 2000. 1.383 1.394 1.394 2500. 1.372 1.385 1.388 3000. 1.360 1.375 1.381 3500. 1.349 1.365 1.375 4000. 1.336 1.354 1.367 4500. 1.324 1.344 1.360 5000. 1.311 1.333 1.352 5500. 1.298 1.322 1.344 6000. 1.285 1.311 1.336 6500. 1.272 1.299 1.328 7000. 1.259 1.288 1.320 7500. 1.248 1.276 1.311 8000. 1.236 1.265 1.303 8500. 1.224 1.253 1.294 9000. 1.212 1.242 1.286 9500. 1.200 1.230 1.277 10000. 1.188 1.219 1.268 10500. 1.176 1.207 1.259 11000. 1.166 1.196 1.251 11500. 1.159 1.184 1.242 12000. 1.153 1.173 1.233 12500. 1.146 1.161 1.224 13000. 1.139 1.149 1.215 13500. 1.132 1.141 1.206 14000. 1.125 1.134 1.197 14500. 1.118 1.126 1.188 15000. 1.115 1.121 1.179 15500. 1.113 1.119 1.170 16000. 1.111 1.116 1.162 16500. 1.110 1.114 1.153 17000. 1.108 1.112 1.145 17500. 1.107 1.111 1.138 18000. 1.105 1.109 1.131 18500. 1.103 1.107 1.124 19000. 1.102 1.106 1.118 19500. 1.100 1.104 1.114 20000. 1.098 1.103 1.111 20500. 1.096 1.101 1.109 21000. 1.094 1.099 1.108 21500. 1.092 1.098 1.108 22000. 1.090 1.096 1.107 22500. 1.088 1.095 1.106 23000. 1.087 1.093 1.105 23500. 1.086 1.091 1.105 24000. 1.085 1.089 1.104 24500. 1.084 1.087 1.103 25000. 1.083 1.086 1.102 25500. 1.082 1.084 1.101 26000. 1.081 1.082 1.101 26500. 1.081 1.081 1.100 27000. 1.080 1.079 1.099 27500. 1.079 1.077 1.098 28000. 1.078 1.076 1.097 30000. 1.076 1.072 1.094 32500. 1.072 1.069 1.090 35000. 1.067 1.065 1.086 37500. 1.063 1.062 1.083 40000. 1.059 1.059 1.080 42500. 1.056 1.056 1.078 45000. 1.058 1.053 1.076 47500. 1.062 1.050 1.074 50000. 1.065 1.047 1.073 52500. 1.066 1.045 1.073 55000. 1.066 1.044 1.073 57500. 1.065 1.043 1.073 60000. 1.063 1.042 1.074 62500. 1.058 1.041 1.082 65000. 1.052 1.039 1.092 67500. 1.044 1.044 1.101 70000. 1.050 1.059 1.111
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-8 Table B.7 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.06997 1.05387 1.03366 100. 1.04445 1.03004 1.01226 500. 1.04178 1.02822 1.01134 1000. 1.04276 1.02985 1.01342 1500. 1.04508 1.03263 1.01634 2000. 1.04775 1.03566 1.01938 2500. 1.05043 1.03863 1.02227 3000. 1.05310 1.04150 1.02497 3500. 1.05584 1.04434 1.02753 4000. 1.05867 1.04720 1.03002 4500. 1.06161 1.05012 1.03249 5000. 1.06472 1.05312 1.03496 5500. 1.06805 1.05627 1.03747 6000. 1.07164 1.05960 1.04006 6500. 1.07545 1.06311 1.04275 7000. 1.07946 1.06677 1.04553 7500. 1.08363 1.07055 1.04840 8000. 1.08798 1.07444 1.05134 8500. 1.09254 1.07846 1.05435 9000. 1.09734 1.08264 1.05744 9500. 1.10237 1.08700 1.06064 10000. 1.10765 1.09153 1.06393 10500. 1.11318 1.09624 1.06733 11000. 1.11900 1.10114 1.07082 11500. 1.12514 1.10624 1.07440 12000. 1.13166 1.11158 1.07808 12500. 1.13859 1.11713 1.08184 13000. 1.14582 1.12284 1.08566 13500. 1.15314 1.12855 1.08948 14000. 1.16036 1.13409 1.09318 14500. 1.16724 1.13936 1.09666 15000. 1.17345 1.14426 1.09986 15500. 1.17865 1.14864 1.10277 16000. 1.18261 1.15230 1.10536 16500. 1.18524 1.15519 1.10760 17000. 1.18651 1.15730 1.10944 17500. 1.18645 1.15859 1.11087 18000. 1.18519 1.15901 1.11190 18500. 1.18296 1.15859 1.11252 19000. 1.17998 1.15738 1.11275 19500. 1.17646 1.15546 1.11258 20000. 1.17253 1.15294 1.11198 20500. 1.16831 1.14993 1.11095 21000. 1.16389 1.14656 1.10949 21500. 1.15934 1.14290 1.10765 22000. 1.15454 1.13904 1.10546 22500. 1.14974 1.13504 1.10297 23000. 1.14493 1.13094 1.10021 23500. 1.14012 1.12665 1.09724 24000. 1.13530 1.12236 1.09409 24500. 1.13049 1.11808 1.09081 25000. 1.12568 1.11379 1.08741 25500. 1.12087 1.10955 1.08394 26000. 1.11607 1.10532 1.08042 26500. 1.11126 1.10108 1.07687 27000. 1.10646 1.09685 1.07329 27500. 1.10165 1.09261 1.06965 30000. 1.07741 1.07156 1.05163 32500. 1.05294 1.05062 1.03405 35000. 1.02826 1.02978 1.01681 37500. 1.00341 1.00907 0.99994 40000. 0.97844 0.98851 0.98344 42500. 0.95345 0.96817 0.96734 45000. 0.92860 0.94811 0.95167 47500. 0.90404 0.92839 0.93647 50000. 0.87998 0.90910 0.92176 52500. 0.85662 0.89036 0.90757 55000. 0.83420 0.87226 0.89395 57500. 0.81297 0.85490 0.88090 60000. 0.79314 0.83839 0.86846 62500. 0.77490 0.82282 0.85664 65000. 0.75838 0.80825 0.84546 67500. 0.74367 0.79477 0.83494 70000. 0.73075 0.78239 0.82508
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-9 Table B.8 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.361 1.340 1.330 100. 1.361 1.341 1.326 500. 1.356 1.338 1.322 1000. 1.350 1.334 1.318 1500. 1.342 1.328 1.313 2000. 1.334 1.322 1.309 2500. 1.324 1.314 1.304 3000. 1.315 1.307 1.299 3500. 1.305 1.299 1.294 4000. 1.294 1.291 1.289 4500. 1.284 1.282 1.283 5000. 1.273 1.273 1.278 5500. 1.262 1.264 1.273 6000. 1.250 1.255 1.268 6500. 1.241 1.247 1.263 7000. 1.233 1.241 1.257 7500. 1.225 1.234 1.252 8000. 1.218 1.228 1.247 8500. 1.210 1.222 1.242 9000. 1.204 1.215 1.237 9500. 1.199 1.209 1.231 10000. 1.194 1.203 1.226 10500. 1.189 1.197 1.221 11000. 1.183 1.191 1.216 11500. 1.178 1.185 1.211 12000. 1.172 1.179 1.206 12500. 1.166 1.173 1.201 13000. 1.161 1.167 1.196 13500. 1.155 1.160 1.191 14000. 1.151 1.154 1.186 14500. 1.147 1.149 1.181 15000. 1.144 1.146 1.176 15500. 1.141 1.143 1.170 16000. 1.140 1.141 1.165 16500. 1.139 1.139 1.159 17000. 1.138 1.137 1.154 17500. 1.136 1.136 1.148 18000. 1.135 1.134 1.143 18500. 1.133 1.132 1.137 19000. 1.131 1.130 1.132 19500. 1.129 1.129 1.130 20000. 1.126 1.127 1.129 20500. 1.124 1.125 1.128 21000. 1.121 1.123 1.127 21500. 1.118 1.121 1.126 22000. 1.115 1.119 1.125 22500. 1.113 1.117 1.124 23000. 1.112 1.114 1.123 23500. 1.111 1.112 1.122 24000. 1.110 1.110 1.121 24500. 1.109 1.108 1.120 25000. 1.108 1.106 1.119 25500. 1.107 1.104 1.118 26000. 1.106 1.102 1.117 26500. 1.105 1.100 1.116 27000. 1.104 1.098 1.115 27500. 1.103 1.096 1.114 30000. 1.097 1.090 1.109 32500. 1.092 1.086 1.104 35000. 1.086 1.082 1.099 37500. 1.079 1.078 1.095 40000. 1.076 1.073 1.091 42500. 1.077 1.069 1.088 45000. 1.079 1.064 1.086 47500. 1.081 1.060 1.084 50000. 1.081 1.056 1.082 52500. 1.081 1.054 1.081 55000. 1.078 1.054 1.080 57500. 1.074 1.054 1.080 60000. 1.068 1.052 1.081 62500. 1.061 1.050 1.084 65000. 1.053 1.047 1.095 67500. 1.051 1.057 1.106 70000. 1.070 1.073 1.118
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-10 Table B.9 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.04366 1.02973 1.01135 100. 1.01839 1.00607 0.99001 500. 1.01598 1.00452 0.98940 1000. 1.01734 1.00660 0.99199 1500. 1.02013 1.00989 0.99547 2000. 1.02328 1.01345 0.99910 2500. 1.02645 1.01697 1.00258 3000. 1.02966 1.02041 1.00586 3500. 1.03297 1.02386 1.00902 4000. 1.03640 1.02735 1.01213 4500. 1.03999 1.03092 1.01522 5000. 1.04379 1.03462 1.01833 5500. 1.04786 1.03850 1.02149 6000. 1.05223 1.04260 1.02475 6500. 1.05686 1.04691 1.02813 7000. 1.06173 1.05140 1.03163 7500. 1.06679 1.05602 1.03522 8000. 1.07207 1.06079 1.03890 8500. 1.07761 1.06572 1.04267 9000. 1.08343 1.07084 1.04654 9500. 1.08955 1.07618 1.05052 10000. 1.09599 1.08174 1.05464 10500. 1.10276 1.08753 1.05888 11000. 1.10990 1.09355 1.06324 11500. 1.11751 1.09985 1.06773 12000. 1.12567 1.10647 1.07234 12500. 1.13438 1.11341 1.07707 13000. 1.14350 1.12058 1.08190 13500. 1.15265 1.12778 1.08674 14000. 1.16143 1.13484 1.09146 14500. 1.16948 1.14154 1.09595 15000. 1.17627 1.14768 1.10017 15500. 1.18139 1.15300 1.10407 16000. 1.18476 1.15730 1.10758 16500. 1.18648 1.16044 1.11063 17000. 1.18672 1.16242 1.11316 17500. 1.18572 1.16330 1.11514 18000. 1.18375 1.16314 1.11657 18500. 1.18104 1.16203 1.11744 19000. 1.17775 1.16010 1.11774 19500. 1.17401 1.15754 1.11747 20000. 1.16990 1.15449 1.11663 20500. 1.16551 1.15108 1.11528 21000. 1.16093 1.14738 1.11343 21500. 1.15599 1.14347 1.11118 22000. 1.15106 1.13939 1.10856 22500. 1.14612 1.13520 1.10567 23000. 1.14114 1.13092 1.10255 23500. 1.13616 1.12646 1.09926 24000. 1.13119 1.12200 1.09583 24500. 1.12621 1.11753 1.09230 25000. 1.12123 1.11307 1.08869 25500. 1.11621 1.10867 1.08504 26000. 1.11118 1.10426 1.08135 26500. 1.10616 1.09986 1.07765 27500. 1.09611 1.09105 1.07006 30000. 1.07062 1.06906 1.05144 32500. 1.04475 1.04707 1.03318 35000. 1.01850 1.02506 1.01522 37500. 0.99191 1.00307 0.99757 40000. 0.96509 0.98113 0.98024 42500. 0.93817 0.95932 0.96326 45000. 0.91133 0.93773 0.94668 47500. 0.88482 0.91645 0.93053 50000. 0.85888 0.89560 0.91487 52500. 0.83384 0.87534 0.89973 55000. 0.81000 0.85581 0.88517 57500. 0.78768 0.83716 0.87121 60000. 0.76715 0.81952 0.85789 62500. 0.74862 0.80302 0.84525 65000. 0.73221 0.78775 0.83333 67500. 0.71794 0.77379 0.82214 70000. 0.70573 0.76118 0.81169
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-11 Table B.10 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.318 1.309 1.319 100. 1.317 1.304 1.315 500. 1.313 1.300 1.311 1000. 1.309 1.294 1.306 1500. 1.305 1.289 1.301 2000. 1.300 1.283 1.296 2500. 1.294 1.277 1.290 3000. 1.288 1.271 1.285 3500. 1.283 1.265 1.280 4000. 1.277 1.258 1.274 4500. 1.270 1.252 1.269 5000. 1.264 1.245 1.263 5500. 1.258 1.239 1.257 6000. 1.251 1.232 1.252 6500. 1.244 1.226 1.246 7000. 1.237 1.219 1.241 7500. 1.230 1.212 1.235 8000. 1.223 1.206 1.230 8500. 1.216 1.199 1.224 9000. 1.208 1.192 1.219 9500. 1.201 1.186 1.213 10000. 1.193 1.179 1.208 10500. 1.186 1.172 1.202 11000. 1.178 1.165 1.197 11500. 1.170 1.159 1.191 12000. 1.162 1.152 1.186 12500. 1.154 1.145 1.181 13000. 1.146 1.138 1.175 13500. 1.138 1.131 1.170 14000. 1.129 1.124 1.165 14500. 1.121 1.116 1.159 15000. 1.113 1.108 1.153 15500. 1.105 1.102 1.148 16000. 1.105 1.096 1.142 16500. 1.106 1.092 1.136 17000. 1.105 1.092 1.130 17500. 1.103 1.092 1.124 18000. 1.104 1.092 1.118 18500. 1.104 1.092 1.113 19000. 1.103 1.092 1.108 19500. 1.102 1.091 1.104 20000. 1.100 1.090 1.100 20500. 1.098 1.089 1.097 21000. 1.097 1.088 1.096 21500. 1.095 1.087 1.096 22000. 1.093 1.085 1.095 22500. 1.091 1.084 1.095 23000. 1.089 1.082 1.094 23500. 1.088 1.081 1.094 24000. 1.086 1.079 1.093 24500. 1.085 1.077 1.092 25000. 1.083 1.076 1.091 25500. 1.082 1.075 1.091 26000. 1.082 1.074 1.090 26500. 1.081 1.073 1.089 27500. 1.080 1.071 1.087 30000. 1.078 1.069 1.083 32500. 1.076 1.068 1.079 35000. 1.074 1.066 1.076 37500. 1.076 1.064 1.073 40000. 1.082 1.062 1.070 42500. 1.086 1.060 1.068 45000. 1.090 1.058 1.066 47500. 1.091 1.061 1.065 50000. 1.091 1.064 1.064 52500. 1.089 1.065 1.064 55000. 1.085 1.065 1.064 57500. 1.078 1.064 1.064 60000. 1.070 1.061 1.065 62500. 1.061 1.057 1.067 65000. 1.051 1.052 1.069 67500. 1.042 1.046 1.081 70000. 1.060 1.058 1.092
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-12 Table B.11 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.03879 1.02603 1.00830 100. 1.01353 1.00231 0.98693 500. 1.01120 1.00090 0.98651 1000. 1.01282 1.00329 0.98946 1500. 1.01589 1.00695 0.99330 2000. 1.01932 1.01087 0.99729 2500. 1.02277 1.01473 1.00110 3000. 1.02631 1.01854 1.00471 3500. 1.02997 1.02238 1.00821 4000. 1.03378 1.02629 1.01167 4500. 1.03779 1.03031 1.01512 5000. 1.04206 1.03449 1.01861 5500. 1.04666 1.03890 1.02217 6000. 1.05159 1.04356 1.02584 6500. 1.05681 1.04844 1.02965 7000. 1.06227 1.05351 1.03356 7500. 1.06797 1.05873 1.03758 8000. 1.07394 1.06412 1.04168 8500. 1.08021 1.06971 1.04589 9000. 1.08682 1.07554 1.05023 9500. 1.09380 1.08161 1.05470 10000. 1.10116 1.08794 1.05931 10500. 1.10895 1.09453 1.06407 11000. 1.11727 1.10142 1.06895 11500. 1.12622 1.10868 1.07398 12000. 1.13582 1.11632 1.07914 12500. 1.14592 1.12429 1.08444 13000. 1.15604 1.13239 1.08977 13500. 1.16570 1.14036 1.09502 14000. 1.17434 1.14790 1.10004 14500. 1.18142 1.15481 1.10477 15000. 1.18663 1.16075 1.10917 15500. 1.18990 1.16544 1.11315 16000. 1.19143 1.16875 1.11662 16500. 1.19155 1.17076 1.11952 17000. 1.19057 1.17157 1.12181 17500. 1.18870 1.17129 1.12350 18000. 1.18611 1.17004 1.12457 18500. 1.18291 1.16799 1.12501 19000. 1.17921 1.16534 1.12482 19500. 1.17510 1.16221 1.12403 20000. 1.17065 1.15872 1.12267 20500. 1.16596 1.15493 1.12080 21000. 1.16085 1.15092 1.11848 21500. 1.15573 1.14673 1.11579 22000. 1.15062 1.14241 1.11281 22500. 1.14551 1.13800 1.10960 23000. 1.14035 1.13340 1.10622 23500. 1.13519 1.12880 1.10270 24000. 1.13003 1.12420 1.09908 24500. 1.12487 1.11960 1.09539 25000. 1.11971 1.11500 1.09165 25500. 1.11447 1.11045 1.08788 26000. 1.10923 1.10591 1.08408 27500. 1.09351 1.09227 1.07245 30000. 1.06684 1.06947 1.05353 32500. 1.03971 1.04662 1.03494 35000. 1.01213 1.02372 1.01664 37500. 0.98419 1.00081 0.99865 40000. 0.95601 0.97795 0.98099 42500. 0.92777 0.95523 0.96369 45000. 0.89970 0.93274 0.94681 47500. 0.87211 0.91062 0.93038 50000. 0.84532 0.88902 0.91448 52500. 0.81969 0.86812 0.89913 55000. 0.79559 0.84809 0.88438 57500. 0.77336 0.82909 0.87028 60000. 0.75326 0.81127 0.85686 62500. 0.73545 0.79477 0.84417 65000. 0.72000 0.77967 0.83224 67500. 0.70685 0.76604 0.82108 70000. 0.69582 0.75387 0.81070
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-13 Table B.12 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.318 1.307 1.270 100. 1.318 1.308 1.272 500. 1.313 1.304 1.271 1000. 1.306 1.299 1.269 1500. 1.301 1.292 1.266 2000. 1.295 1.285 1.262 2500. 1.289 1.277 1.258 3000. 1.282 1.269 1.253 3500. 1.276 1.260 1.248 4000. 1.269 1.251 1.242 4500. 1.262 1.242 1.236 5000. 1.255 1.232 1.230 5500. 1.247 1.223 1.224 6000. 1.240 1.213 1.217 6500. 1.232 1.203 1.211 7000. 1.224 1.192 1.204 7500. 1.216 1.182 1.197 8000. 1.208 1.172 1.190 8500. 1.199 1.161 1.183 9000. 1.191 1.152 1.176 9500. 1.182 1.146 1.168 10000. 1.174 1.140 1.161 10500. 1.165 1.134 1.153 11000. 1.156 1.128 1.146 11500. 1.147 1.122 1.138 12000. 1.138 1.116 1.133 12500. 1.129 1.110 1.128 13000. 1.120 1.104 1.123 13500. 1.115 1.097 1.118 14000. 1.138 1.091 1.113 14500. 1.152 1.087 1.108 15000. 1.158 1.083 1.102 15500. 1.158 1.084 1.097 16000. 1.156 1.094 1.091 16500. 1.152 1.100 1.088 17000. 1.152 1.102 1.087 17500. 1.151 1.102 1.085 18000. 1.149 1.100 1.084 18500. 1.147 1.099 1.082 19000. 1.144 1.097 1.081 19500. 1.142 1.095 1.080 20000. 1.139 1.093 1.079 20500. 1.137 1.092 1.078 21000. 1.135 1.091 1.077 21500. 1.132 1.090 1.077 22000. 1.129 1.089 1.076 22500. 1.127 1.087 1.075 23000. 1.125 1.086 1.075 23500. 1.122 1.085 1.075 24000. 1.120 1.083 1.074 24500. 1.117 1.082 1.074 25000. 1.115 1.081 1.074 25500. 1.112 1.080 1.074 26000. 1.110 1.079 1.073 27500. 1.102 1.075 1.073 30000. 1.090 1.074 1.071 32500. 1.092 1.072 1.070 35000. 1.096 1.071 1.068 37500. 1.099 1.070 1.067 40000. 1.101 1.072 1.066 42500. 1.103 1.075 1.064 45000. 1.105 1.078 1.063 47500. 1.104 1.079 1.062 50000. 1.101 1.080 1.061 52500. 1.097 1.079 1.060 55000. 1.090 1.077 1.058 57500. 1.081 1.073 1.057 60000. 1.071 1.069 1.055 62500. 1.059 1.063 1.057 65000. 1.048 1.056 1.069 67500. 1.047 1.049 1.081 70000. 1.064 1.061 1.092
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-14 Table B.13 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.05587 1.04582 1.03154 100. 1.03059 1.02198 1.01000 500. 1.02991 1.02211 1.01086 1000. 1.03405 1.02683 1.01569 1500. 1.03981 1.03298 1.02152 2000. 1.04594 1.03936 1.02741 2500. 1.05225 1.04579 1.03314 3000. 1.05886 1.05234 1.03877 3500. 1.06589 1.05912 1.04442 4000. 1.07343 1.06623 1.05015 4500. 1.08152 1.07372 1.05603 5000. 1.09011 1.08154 1.06207 5500. 1.09918 1.08968 1.06827 6000. 1.10879 1.09816 1.07461 6500. 1.11904 1.10705 1.08114 7000. 1.13002 1.11640 1.08787 7500. 1.14175 1.12621 1.09483 8000. 1.15421 1.13647 1.10198 8500. 1.16727 1.14710 1.10930 9000. 1.18039 1.15793 1.11669 9500. 1.19292 1.16860 1.12402 10000. 1.20406 1.17867 1.13113 10500. 1.21330 1.18772 1.13788 11000. 1.22037 1.19537 1.14410 11500. 1.22524 1.20136 1.14962 12000. 1.22816 1.20562 1.15432 12500. 1.22948 1.20823 1.15810 13000. 1.22952 1.20938 1.16090 13500. 1.22845 1.20929 1.16275 14000. 1.22648 1.20819 1.16368 14500. 1.22377 1.20629 1.16376 15000. 1.22046 1.20376 1.16306 15500. 1.21666 1.20072 1.16168 16000. 1.21247 1.19729 1.15971 16500. 1.20799 1.19355 1.15727 17000. 1.20331 1.18955 1.15445 17500. 1.19848 1.18536 1.15134 18000. 1.19336 1.18104 1.14800 18500. 1.18825 1.17662 1.14448 19000. 1.18313 1.17213 1.14083 19500. 1.17802 1.16748 1.13707 20000. 1.17290 1.16284 1.13324 20500. 1.16780 1.15823 1.12935 21000. 1.16270 1.15361 1.12543 21500. 1.15759 1.14900 1.12149 22000. 1.15249 1.14438 1.11754 22500. 1.14739 1.13977 1.11352 25000. 1.12147 1.11690 1.09371 27500. 1.09509 1.09399 1.07437 30000. 1.06823 1.07101 1.05534 32500. 1.04089 1.04798 1.03660 35000. 1.01311 1.02490 1.01815 37500. 0.98496 1.00180 1.00000 40000. 0.95659 0.97876 0.98219 42500. 0.92817 0.95587 0.96475 45000. 0.89995 0.93324 0.94774 47500. 0.87225 0.91099 0.93121 50000. 0.84539 0.88930 0.91521 52500. 0.81975 0.86833 0.89979 55000. 0.79569 0.84827 0.88498 57500. 0.77356 0.82928 0.87083 60000. 0.75360 0.81151 0.85740 62500. 0.73597 0.79509 0.84471 65000. 0.72072 0.78010 0.83280 67500. 0.70775 0.76660 0.82168 70000. 0.69692 0.75458 0.81135
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-15 Table B.14 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.307 1.292 1.257 100. 1.306 1.293 1.258 500. 1.302 1.287 1.256 1000. 1.296 1.280 1.252 1500. 1.289 1.272 1.248 2000. 1.282 1.262 1.242 2500. 1.274 1.252 1.236 3000. 1.266 1.242 1.230 3500. 1.258 1.231 1.223 4000. 1.250 1.220 1.216 4500. 1.241 1.208 1.208 5000. 1.232 1.196 1.201 5500. 1.222 1.184 1.193 6000. 1.213 1.172 1.184 6500. 1.203 1.159 1.176 7000. 1.193 1.149 1.168 7500. 1.183 1.143 1.159 8000. 1.172 1.136 1.150 8500. 1.162 1.128 1.142 9000. 1.151 1.121 1.136 9500. 1.140 1.113 1.130 10000. 1.135 1.105 1.123 10500. 1.152 1.098 1.117 11000. 1.160 1.090 1.110 11500. 1.161 1.088 1.103 12000. 1.160 1.097 1.097 12500. 1.157 1.101 1.090 13000. 1.153 1.102 1.086 13500. 1.150 1.102 1.085 14000. 1.146 1.101 1.083 14500. 1.144 1.100 1.082 15000. 1.142 1.098 1.082 15500. 1.139 1.096 1.081 16000. 1.137 1.095 1.080 16500. 1.135 1.093 1.080 17000. 1.133 1.092 1.079 17500. 1.131 1.091 1.079 18000. 1.129 1.089 1.078 18500. 1.127 1.088 1.078 19000. 1.124 1.087 1.077 19500. 1.122 1.086 1.077 20000. 1.120 1.084 1.077 20500. 1.118 1.083 1.076 21000. 1.116 1.082 1.076 21500. 1.114 1.080 1.076 22000. 1.112 1.079 1.076 22500. 1.110 1.078 1.075 25000. 1.099 1.075 1.074 27500. 1.088 1.073 1.073 30000. 1.081 1.071 1.072 32500. 1.082 1.070 1.070 35000. 1.085 1.068 1.068 37500. 1.088 1.066 1.066 40000. 1.090 1.065 1.065 42500. 1.091 1.066 1.063 45000. 1.093 1.068 1.060 47500. 1.092 1.069 1.059 50000. 1.089 1.070 1.058 52500. 1.085 1.069 1.056 55000. 1.078 1.067 1.055 57500. 1.070 1.064 1.053 60000. 1.060 1.059 1.051 62500. 1.050 1.054 1.058 65000. 1.039 1.048 1.070 67500. 1.046 1.045 1.081 70000. 1.062 1.061 1.093
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-16 Table B.15 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.06422 1.04771 1.02961 100. 1.04133 1.02662 1.01099 500. 1.04064 1.02646 1.01126 1000. 1.04386 1.02976 1.01435 1500. 1.04842 1.03410 1.01814 2000. 1.05350 1.03877 1.02204 2500. 1.05887 1.04357 1.02591 3000. 1.06446 1.04842 1.02970 3500. 1.07025 1.05332 1.03341 4000. 1.07620 1.05824 1.03705 4500. 1.08214 1.06316 1.04062 5000. 1.08774 1.06793 1.04409 5500. 1.09274 1.07235 1.04742 6000. 1.09709 1.07632 1.05052 6500. 1.10086 1.07981 1.05334 7000. 1.10414 1.08290 1.05586 7500. 1.10701 1.08565 1.05811 8000. 1.10958 1.08811 1.06014 8500. 1.11197 1.09036 1.06199 9000. 1.11426 1.09246 1.06369 9500. 1.11653 1.09446 1.06527 10000. 1.11883 1.09642 1.06676 10500. 1.12119 1.09836 1.06817 11000. 1.12364 1.10033 1.06952 11500. 1.12620 1.10233 1.07084 12000. 1.12890 1.10441 1.07215 12500. 1.13174 1.10657 1.07346 13000. 1.13477 1.10883 1.07480 13500. 1.13798 1.11121 1.07617 14000. 1.14139 1.11369 1.07759 14500. 1.14501 1.11626 1.07903 15000. 1.14879 1.11892 1.08050 15500. 1.15272 1.12163 1.08197 16000. 1.15667 1.12434 1.08342 16500. 1.16055 1.12699 1.08481 17000. 1.16417 1.12953 1.08612 17500. 1.16736 1.13187 1.08731 18000. 1.17000 1.13395 1.08837 18500. 1.17193 1.13568 1.08928 19000. 1.17307 1.13698 1.09002 19500. 1.17338 1.13782 1.09057 20000. 1.17291 1.13816 1.09091 20500. 1.17167 1.13798 1.09103 21000. 1.16975 1.13730 1.09090 21500. 1.16728 1.13613 1.09053 22000. 1.16436 1.13449 1.08989 22500. 1.16109 1.13244 1.08899 23000. 1.15754 1.13001 1.08784 23500. 1.15378 1.12728 1.08644 24000. 1.14984 1.12429 1.08481 24500. 1.14577 1.12111 1.08296 25000. 1.14163 1.11776 1.08089 25500. 1.13730 1.11428 1.07862 26000. 1.13296 1.11070 1.07619 26500. 1.12863 1.10705 1.07359 27000. 1.12429 1.10335 1.07086 27500. 1.11996 1.09960 1.06803 28000. 1.11567 1.09578 1.06510 28500. 1.11138 1.09196 1.06210 29000. 1.10708 1.08813 1.05904 29500. 1.10279 1.08431 1.05594 30000. 1.09850 1.08049 1.05280 30500. 1.09420 1.07674 1.04964 31000. 1.08990 1.07298 1.04646 31500. 1.08560 1.06923 1.04327 32000. 1.08130 1.06547 1.04008 32500. 1.07700 1.06172 1.03689 33000. 1.07270 1.05801 1.03370 35000. 1.05548 1.04317 1.02093 37500. 1.03393 1.02484 1.00544 40000. 1.01238 1.00675 0.99035 42500. 0.99088 0.98893 0.97566 45000. 0.96948 0.97140 0.96140 47500. 0.94827 0.95420 0.94759 50000. 0.92732 0.93738 0.93424 52500. 0.90677 0.92097 0.92137 55000. 0.88672 0.90503 0.90899 57500. 0.86731 0.88963 0.89713 60000. 0.84867 0.87481 0.88579 62500. 0.83094 0.86061 0.87497 65000. 0.81423 0.84710 0.86469 67500. 0.79865 0.83431 0.85493 70000. 0.78428 0.82227 0.84571
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-17 Table B.16 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.461 1.474 1.473 100. 1.454 1.468 1.468 500. 1.445 1.460 1.463 1000. 1.435 1.451 1.456 1500. 1.423 1.441 1.449 2000. 1.410 1.430 1.441 2500. 1.397 1.418 1.432 3000. 1.383 1.406 1.422 3500. 1.369 1.394 1.413 4000. 1.355 1.382 1.404 4500. 1.342 1.370 1.394 5000. 1.328 1.358 1.385 5500. 1.318 1.346 1.375 6000. 1.308 1.335 1.366 6500. 1.300 1.324 1.357 7000. 1.291 1.314 1.349 7500. 1.284 1.304 1.340 8000. 1.276 1.294 1.332 8500. 1.269 1.284 1.324 9000. 1.262 1.278 1.316 9500. 1.255 1.273 1.308 10000. 1.248 1.268 1.301 10500. 1.241 1.263 1.293 11000. 1.235 1.257 1.286 11500. 1.229 1.252 1.280 12000. 1.223 1.247 1.276 12500. 1.218 1.242 1.271 13000. 1.212 1.237 1.267 13500. 1.206 1.232 1.263 14000. 1.200 1.227 1.258 14500. 1.194 1.222 1.254 15000. 1.188 1.216 1.250 15500. 1.181 1.211 1.245 16000. 1.174 1.205 1.241 16500. 1.168 1.199 1.236 17000. 1.162 1.193 1.232 17500. 1.156 1.187 1.227 18000. 1.151 1.180 1.222 18500. 1.145 1.173 1.217 19000. 1.140 1.167 1.212 19500. 1.135 1.162 1.207 20000. 1.130 1.157 1.202 20500. 1.126 1.153 1.197 21000. 1.123 1.149 1.192 21500. 1.119 1.145 1.187 22000. 1.116 1.141 1.182 22500. 1.113 1.138 1.178 23000. 1.112 1.135 1.174 23500. 1.110 1.132 1.170 24000. 1.109 1.129 1.166 24500. 1.108 1.127 1.163 25000. 1.106 1.125 1.160 25500. 1.104 1.122 1.157 26000. 1.103 1.120 1.154 26500. 1.101 1.118 1.151 27000. 1.100 1.117 1.149 27500. 1.098 1.115 1.147 28000. 1.096 1.113 1.145 28500. 1.095 1.111 1.143 29000. 1.093 1.110 1.142 29500. 1.092 1.108 1.140 30000. 1.090 1.106 1.139 30500. 1.088 1.104 1.137 31000. 1.086 1.102 1.136 31500. 1.085 1.101 1.134 32000. 1.083 1.099 1.133 32500. 1.081 1.097 1.131 33000. 1.079 1.095 1.130 35000. 1.073 1.089 1.125 37500. 1.064 1.080 1.119 40000. 1.056 1.072 1.113 42500. 1.049 1.064 1.107 45000. 1.043 1.058 1.102 47500. 1.041 1.052 1.100 50000. 1.039 1.048 1.107 52500. 1.037 1.044 1.116 55000. 1.038 1.043 1.126 57500. 1.041 1.042 1.136 60000. 1.043 1.042 1.146 62500. 1.043 1.054 1.157 65000. 1.041 1.069 1.168 67500. 1.045 1.084 1.179 70000. 1.064 1.098 1.190
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-18 Table B.17 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.12421 1.10266 1.07803 100. 1.09827 1.07863 1.05662 500. 1.09461 1.07571 1.05444 1000. 1.09403 1.07558 1.05460 1500. 1.09459 1.07640 1.05545 2000. 1.09546 1.07744 1.05642 2500. 1.09642 1.07852 1.05733 3000. 1.09740 1.07955 1.05816 3500. 1.09841 1.08054 1.05891 4000. 1.09948 1.08154 1.05961 4500. 1.10063 1.08256 1.06028 5000. 1.10188 1.08363 1.06095 5500. 1.10322 1.08476 1.06163 6000. 1.10466 1.08595 1.06232 6500. 1.10618 1.08719 1.06305 7000. 1.10778 1.08848 1.06381 7500. 1.10947 1.08983 1.06462 8000. 1.11124 1.09124 1.06546 8500. 1.11311 1.09272 1.06635 9000. 1.11508 1.09427 1.06729 9500. 1.11715 1.09590 1.06827 10000. 1.11933 1.09761 1.06929 10500. 1.12161 1.09938 1.07035 11000. 1.12401 1.10124 1.07144 11500. 1.12653 1.10317 1.07257 12000. 1.12920 1.10520 1.07373 12500. 1.13204 1.10733 1.07494 13000. 1.13505 1.10958 1.07621 13500. 1.13825 1.11193 1.07753 14000. 1.14165 1.11440 1.07890 14500. 1.14523 1.11697 1.08032 15000. 1.14899 1.11962 1.08176 15500. 1.15289 1.12232 1.08321 16000. 1.15682 1.12502 1.08463 16500. 1.16066 1.12765 1.08600 17000. 1.16424 1.13017 1.08727 17500. 1.16740 1.13250 1.08844 18000. 1.17003 1.13455 1.08947 18500. 1.17196 1.13625 1.09036 19000. 1.17313 1.13753 1.09107 19500. 1.17349 1.13836 1.09158 20000. 1.17309 1.13870 1.09190 20500. 1.17195 1.13853 1.09200 21000. 1.17014 1.13787 1.09185 21500. 1.16776 1.13673 1.09145 22000. 1.16493 1.13514 1.09081 22500. 1.16174 1.13313 1.08990 23000. 1.15825 1.13074 1.08874 23500. 1.15454 1.12805 1.08734 24000. 1.15065 1.12510 1.08571 24500. 1.14661 1.12194 1.08386 25000. 1.14248 1.11862 1.08180 25500. 1.13814 1.11516 1.07954 26000. 1.13381 1.11160 1.07711 26500. 1.12947 1.10796 1.07452 27000. 1.12514 1.10426 1.07180 27500. 1.12080 1.10052 1.06897 28000. 1.11650 1.09675 1.06605 28500. 1.11220 1.09291 1.06305 29000. 1.10789 1.08906 1.05999 29500. 1.10359 1.08521 1.05689 30000. 1.09929 1.08137 1.05375 30500. 1.09498 1.07760 1.05059 31000. 1.09067 1.07384 1.04740 31500. 1.08636 1.07007 1.04421 32000. 1.08205 1.06631 1.04101 32500. 1.07774 1.06254 1.03781 33000. 1.07342 1.05882 1.03461 33500. 1.06911 1.05510 1.03142 35000. 1.05616 1.04393 1.02182 37500. 1.03455 1.02556 1.00627 40000. 1.01295 1.00742 0.99113 42500. 0.99139 0.98955 0.97640 45000. 0.96994 0.97197 0.96210 47500. 0.94868 0.95474 0.94825 50000. 0.92769 0.93787 0.93487 52500. 0.90710 0.92143 0.92197 55000. 0.88702 0.90547 0.90957 57500. 0.86758 0.89004 0.89768 60000. 0.84893 0.87519 0.88632 62500. 0.83119 0.86099 0.87548 65000. 0.81448 0.84746 0.86519 67500. 0.79891 0.83466 0.85542 70000. 0.78456 0.82262 0.84620
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-19 Table B.18 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.406 1.422 1.430 100. 1.401 1.419 1.427 500. 1.396 1.414 1.424 1000. 1.389 1.408 1.420 1500. 1.382 1.402 1.416 2000. 1.373 1.394 1.410 2500. 1.365 1.387 1.404 3000. 1.356 1.379 1.398 3500. 1.347 1.371 1.391 4000. 1.337 1.363 1.385 4500. 1.328 1.355 1.378 5000. 1.319 1.346 1.371 5500. 1.310 1.338 1.365 6000. 1.304 1.329 1.358 6500. 1.297 1.321 1.351 7000. 1.291 1.312 1.344 7500. 1.284 1.303 1.337 8000. 1.278 1.294 1.330 8500. 1.271 1.285 1.323 9000. 1.264 1.279 1.315 9500. 1.257 1.274 1.308 10000. 1.251 1.269 1.301 10500. 1.244 1.264 1.294 11000. 1.238 1.259 1.287 11500. 1.232 1.254 1.281 12000. 1.226 1.249 1.276 12500. 1.220 1.244 1.272 13000. 1.214 1.239 1.268 13500. 1.208 1.234 1.263 14000. 1.202 1.229 1.259 14500. 1.196 1.224 1.255 15000. 1.190 1.218 1.251 15500. 1.184 1.213 1.246 16000. 1.177 1.207 1.242 16500. 1.171 1.201 1.237 17000. 1.165 1.195 1.233 17500. 1.159 1.189 1.228 18000. 1.153 1.182 1.223 18500. 1.148 1.175 1.218 19000. 1.142 1.169 1.213 19500. 1.137 1.163 1.208 20000. 1.133 1.159 1.202 20500. 1.128 1.154 1.197 21000. 1.125 1.150 1.192 21500. 1.121 1.146 1.188 22000. 1.118 1.143 1.183 22500. 1.115 1.139 1.179 23000. 1.114 1.136 1.175 23500. 1.113 1.133 1.171 24000. 1.112 1.131 1.167 24500. 1.110 1.128 1.164 25000. 1.109 1.126 1.160 25500. 1.107 1.124 1.157 26000. 1.106 1.121 1.154 26500. 1.104 1.120 1.152 27000. 1.103 1.118 1.149 27500. 1.101 1.116 1.147 28000. 1.099 1.114 1.146 28500. 1.097 1.112 1.144 29000. 1.096 1.110 1.142 29500. 1.094 1.109 1.141 30000. 1.092 1.107 1.139 30500. 1.090 1.105 1.138 31000. 1.089 1.103 1.136 31500. 1.087 1.102 1.135 32000. 1.086 1.100 1.133 32500. 1.084 1.098 1.132 33000. 1.082 1.096 1.130 33500. 1.080 1.095 1.129 35000. 1.075 1.090 1.125 37500. 1.067 1.081 1.119 40000. 1.059 1.073 1.113 42500. 1.051 1.065 1.107 45000. 1.044 1.059 1.102 47500. 1.041 1.054 1.099 50000. 1.039 1.049 1.107 52500. 1.037 1.045 1.116 55000. 1.039 1.043 1.126 57500. 1.042 1.042 1.136 60000. 1.043 1.041 1.146 62500. 1.043 1.054 1.157 65000. 1.042 1.069 1.168 67500. 1.045 1.083 1.179 70000. 1.064 1.098 1.190
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-20 Table B.19 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.09528 1.07797 1.05714 100. 1.06932 1.05377 1.03545 500. 1.06596 1.05116 1.03361 1000. 1.06581 1.05154 1.03434 1500. 1.06694 1.05301 1.03588 2000. 1.06846 1.05478 1.03762 2500. 1.07012 1.05664 1.03934 3000. 1.07186 1.05849 1.04101 3500. 1.07369 1.06036 1.04261 4000. 1.07565 1.06228 1.04420 4500. 1.07774 1.06428 1.04578 5000. 1.07999 1.06637 1.04737 5500. 1.08238 1.06855 1.04899 6000. 1.08489 1.07082 1.05064 6500. 1.08752 1.07317 1.05234 7000. 1.09026 1.07560 1.05408 7500. 1.09312 1.07810 1.05588 8000. 1.09611 1.08069 1.05773 8500. 1.09925 1.08338 1.05965 9000. 1.10252 1.08617 1.06163 9500. 1.10594 1.08907 1.06366 10000. 1.10950 1.09206 1.06575 10500. 1.11321 1.09516 1.06789 11000. 1.11710 1.09838 1.07009 11500. 1.12118 1.10173 1.07234 12000. 1.12550 1.10523 1.07466 12500. 1.13008 1.10889 1.07706 13000. 1.13495 1.11273 1.07954 13500. 1.14014 1.11675 1.08211 14000. 1.14561 1.12095 1.08476 14500. 1.15137 1.12531 1.08747 15000. 1.15735 1.12980 1.09021 15500. 1.16330 1.13431 1.09294 16000. 1.16901 1.13875 1.09563 16500. 1.17421 1.14302 1.09821 17000. 1.17864 1.14692 1.10067 17500. 1.18215 1.15034 1.10295 18000. 1.18458 1.15316 1.10501 18500. 1.18590 1.15530 1.10680 19000. 1.18617 1.15669 1.10829 19500. 1.18554 1.15732 1.10944 20000. 1.18416 1.15721 1.11024 20500. 1.18216 1.15644 1.11065 21000. 1.17965 1.15508 1.11067 21500. 1.17672 1.15319 1.11030 22000. 1.17344 1.15086 1.10955 22500. 1.16986 1.14817 1.10845 23000. 1.16604 1.14520 1.10702 23500. 1.16200 1.14199 1.10527 24000. 1.15780 1.13858 1.10323 24500. 1.15348 1.13502 1.10093 25000. 1.14896 1.13132 1.09840 25500. 1.14437 1.12751 1.09568 26000. 1.13977 1.12363 1.09280 26500. 1.13518 1.11969 1.08979 27000. 1.13058 1.11560 1.08668 27500. 1.12599 1.11151 1.08348 28000. 1.12141 1.10745 1.08021 28500. 1.11683 1.10338 1.07689 29000. 1.11224 1.09932 1.07352 29500. 1.10766 1.09525 1.07013 30000. 1.10308 1.09119 1.06671 30500. 1.09845 1.08716 1.06328 31000. 1.09382 1.08314 1.05985 32500. 1.07992 1.07106 1.04938 35000. 1.05650 1.05099 1.03236 37500. 1.03281 1.03097 1.01566 40000. 1.00890 1.01103 0.99929 42500. 0.98481 0.99120 0.98323 45000. 0.96064 0.97151 0.96752 47500. 0.93648 0.95203 0.95220 50000. 0.91249 0.93283 0.93729 52500. 0.88884 0.91397 0.92282 55000. 0.86573 0.89555 0.90882 57500. 0.84339 0.87767 0.89533 60000. 0.82202 0.86044 0.88237 62500. 0.80187 0.84394 0.86996 65000. 0.78313 0.82827 0.85813 67500. 0.76596 0.81351 0.84690 70000. 0.75047 0.79973 0.83628
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-21 Table B.20 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.484 1.487 1.477 100. 1.482 1.486 1.477 500. 1.475 1.480 1.474 1000. 1.467 1.474 1.470 1500. 1.457 1.466 1.465 2000. 1.446 1.457 1.459 2500. 1.435 1.448 1.453 3000. 1.424 1.438 1.446 3500. 1.412 1.428 1.438 4000. 1.400 1.417 1.431 4500. 1.388 1.407 1.423 5000. 1.376 1.396 1.415 5500. 1.363 1.385 1.407 6000. 1.350 1.374 1.399 6500. 1.338 1.363 1.390 7000. 1.325 1.352 1.382 7500. 1.312 1.341 1.373 8000. 1.299 1.329 1.364 8500. 1.286 1.318 1.356 9000. 1.273 1.307 1.347 9500. 1.260 1.295 1.338 10000. 1.248 1.284 1.329 10500. 1.237 1.272 1.321 11000. 1.225 1.261 1.312 11500. 1.217 1.250 1.303 12000. 1.209 1.238 1.294 12500. 1.200 1.227 1.285 13000. 1.194 1.216 1.276 13500. 1.189 1.206 1.268 14000. 1.185 1.198 1.259 14500. 1.180 1.190 1.250 15000. 1.176 1.183 1.241 15500. 1.172 1.178 1.232 16000. 1.168 1.175 1.224 16500. 1.165 1.171 1.215 17000. 1.161 1.168 1.206 17500. 1.159 1.165 1.197 18000. 1.156 1.162 1.189 18500. 1.154 1.159 1.182 19000. 1.152 1.156 1.176 19500. 1.150 1.154 1.170 20000. 1.148 1.152 1.165 20500. 1.146 1.149 1.160 21000. 1.144 1.147 1.155 21500. 1.142 1.145 1.152 22000. 1.140 1.143 1.151 22500. 1.138 1.142 1.149 23000. 1.135 1.140 1.148 23500. 1.133 1.138 1.147 24000. 1.130 1.136 1.146 24500. 1.128 1.134 1.145 25000. 1.125 1.132 1.143 25500. 1.123 1.130 1.142 26000. 1.120 1.128 1.141 26500. 1.118 1.125 1.140 27000. 1.115 1.123 1.139 27500. 1.113 1.121 1.138 28000. 1.110 1.119 1.137 28500. 1.107 1.117 1.135 29000. 1.105 1.115 1.134 29500. 1.102 1.113 1.133 30000. 1.099 1.111 1.132 30500. 1.097 1.109 1.131 31000. 1.094 1.107 1.129 32500. 1.087 1.101 1.126 35000. 1.074 1.091 1.120 37500. 1.062 1.082 1.114 40000. 1.051 1.073 1.109 42500. 1.041 1.065 1.105 45000. 1.041 1.058 1.101 47500. 1.045 1.052 1.097 50000. 1.049 1.047 1.094 52500. 1.053 1.043 1.092 55000. 1.055 1.040 1.090 57500. 1.056 1.038 1.088 60000. 1.055 1.038 1.087 62500. 1.054 1.038 1.087 65000. 1.050 1.040 1.087 67500. 1.045 1.042 1.092 70000. 1.039 1.046 1.102
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-22 Table B.21 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.09471 1.07777 1.05677 100. 1.06856 1.05339 1.03494 500. 1.06523 1.05085 1.03319 1000. 1.06523 1.05140 1.03411 1500. 1.06658 1.05312 1.03590 2000. 1.06835 1.05518 1.03790 2500. 1.07021 1.05727 1.03987 3000. 1.07207 1.05929 1.04171 3500. 1.07397 1.06126 1.04342 4000. 1.07593 1.06323 1.04505 4500. 1.07798 1.06523 1.04664 5000. 1.08013 1.06728 1.04822 5500. 1.08241 1.06940 1.04981 6000. 1.08486 1.07164 1.05144 6500. 1.08752 1.07401 1.05313 7000. 1.09038 1.07653 1.05491 7500. 1.09342 1.07920 1.05678 8000. 1.09663 1.08200 1.05875 8500. 1.09999 1.08491 1.06079 9000. 1.10350 1.08792 1.06291 9500. 1.10717 1.09105 1.06509 10000. 1.11103 1.09430 1.06734 10500. 1.11508 1.09770 1.06966 11000. 1.11934 1.10124 1.07205 11500. 1.12383 1.10495 1.07452 12000. 1.12857 1.10881 1.07708 12500. 1.13360 1.11285 1.07971 13000. 1.13896 1.11708 1.08243 13500. 1.14470 1.12152 1.08523 14000. 1.15081 1.12617 1.08813 14500. 1.15720 1.13100 1.09109 15000. 1.16375 1.13594 1.09409 15500. 1.17018 1.14087 1.09708 16000. 1.17618 1.14568 1.09999 16500. 1.18143 1.15017 1.10279 17000. 1.18574 1.15420 1.10544 17500. 1.18888 1.15761 1.10788 18000. 1.19077 1.16030 1.11004 18500. 1.19145 1.16217 1.11189 19000. 1.19111 1.16320 1.11340 19500. 1.18990 1.16342 1.11453 20000. 1.18799 1.16288 1.11525 20500. 1.18550 1.16167 1.11555 21000. 1.18253 1.15986 1.11541 21500. 1.17917 1.15755 1.11487 22000. 1.17548 1.15484 1.11392 22500. 1.17150 1.15181 1.11261 23000. 1.16731 1.14852 1.11094 23500. 1.16295 1.14500 1.10894 24000. 1.15830 1.14131 1.10665 24500. 1.15364 1.13749 1.10411 25000. 1.14899 1.13355 1.10135 25500. 1.14431 1.12955 1.09843 26000. 1.13964 1.12537 1.09536 26500. 1.13496 1.12120 1.09218 27000. 1.13029 1.11702 1.08891 27500. 1.12561 1.11284 1.08557 28000. 1.12091 1.10871 1.08218 28500. 1.11620 1.10458 1.07874 29000. 1.11150 1.10046 1.07527 29500. 1.10679 1.09633 1.07179 30000. 1.10209 1.09220 1.06830 32500. 1.07830 1.07164 1.05065 35000. 1.05422 1.05111 1.03346 37500. 1.02985 1.03064 1.01657 40000. 1.00524 1.01022 0.99999 42500. 0.98045 0.98991 0.98375 45000. 0.95557 0.96974 0.96786 47500. 0.93075 0.94979 0.95236 50000. 0.90614 0.93013 0.93729 52500. 0.88195 0.91085 0.92266 55000. 0.85840 0.89205 0.90852 57500. 0.83572 0.87384 0.89490 60000. 0.81417 0.85632 0.88184 62500. 0.79398 0.83961 0.86934 65000. 0.77534 0.82380 0.85744 67500. 0.75842 0.80897 0.84615 70000. 0.74331 0.79519 0.83550
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-23 Table B.22 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.486 1.471 1.436 100. 1.485 1.470 1.434 500. 1.480 1.465 1.430 1000. 1.473 1.460 1.425 1500. 1.464 1.453 1.420 2000. 1.455 1.445 1.414 2500. 1.445 1.436 1.409 3000. 1.435 1.428 1.403 3500. 1.425 1.419 1.397 4000. 1.414 1.410 1.391 4500. 1.403 1.401 1.385 5000. 1.392 1.392 1.379 5500. 1.381 1.384 1.373 6000. 1.373 1.377 1.367 6500. 1.365 1.369 1.361 7000. 1.356 1.361 1.355 7500. 1.347 1.353 1.349 8000. 1.338 1.345 1.342 8500. 1.329 1.337 1.336 9000. 1.320 1.329 1.330 9500. 1.311 1.321 1.323 10000. 1.302 1.313 1.317 10500. 1.293 1.305 1.310 11000. 1.283 1.296 1.304 11500. 1.274 1.288 1.299 12000. 1.264 1.280 1.294 12500. 1.254 1.271 1.288 13000. 1.245 1.263 1.283 13500. 1.234 1.254 1.277 14000. 1.224 1.246 1.272 14500. 1.214 1.237 1.267 15000. 1.204 1.229 1.261 15500. 1.194 1.220 1.255 16000. 1.184 1.212 1.249 16500. 1.176 1.204 1.243 17000. 1.167 1.196 1.237 17500. 1.160 1.189 1.231 18000. 1.153 1.182 1.224 18500. 1.147 1.175 1.218 19000. 1.142 1.169 1.212 19500. 1.137 1.164 1.205 20000. 1.132 1.159 1.199 20500. 1.128 1.154 1.193 21000. 1.124 1.150 1.188 21500. 1.121 1.146 1.183 22000. 1.117 1.142 1.178 22500. 1.114 1.138 1.174 23000. 1.111 1.135 1.170 23500. 1.108 1.132 1.166 24000. 1.105 1.129 1.163 24500. 1.103 1.126 1.160 25000. 1.100 1.123 1.157 25500. 1.097 1.121 1.154 26000. 1.095 1.118 1.152 26500. 1.092 1.116 1.149 27000. 1.090 1.113 1.147 27500. 1.087 1.111 1.144 28000. 1.084 1.108 1.142 28500. 1.081 1.106 1.140 29000. 1.079 1.103 1.138 29500. 1.076 1.101 1.136 30000. 1.073 1.098 1.134 32500. 1.064 1.086 1.124 35000. 1.059 1.074 1.115 37500. 1.053 1.062 1.106 40000. 1.048 1.052 1.097 42500. 1.050 1.047 1.089 45000. 1.050 1.043 1.081 47500. 1.053 1.040 1.075 50000. 1.055 1.036 1.069 52500. 1.057 1.035 1.064 55000. 1.058 1.034 1.064 57500. 1.057 1.035 1.065 60000. 1.055 1.036 1.067 62500. 1.051 1.036 1.073 65000. 1.046 1.036 1.083 67500. 1.040 1.037 1.093 70000. 1.047 1.052 1.103
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-24 Table B.23 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.07017 1.05560 1.03672 100. 1.04418 1.03127 1.01482 500. 1.04109 1.02896 1.01333 1000. 1.04141 1.02988 1.01465 1500. 1.04315 1.03203 1.01691 2000. 1.04535 1.03456 1.01940 2500. 1.04765 1.03714 1.02187 3000. 1.04998 1.03965 1.02420 3500. 1.05238 1.04214 1.02642 4000. 1.05487 1.04466 1.02857 4500. 1.05748 1.04722 1.03069 5000. 1.06022 1.04986 1.03281 5500. 1.06313 1.05260 1.03494 6000. 1.06626 1.05548 1.03712 6500. 1.06962 1.05853 1.03938 7000. 1.07322 1.06176 1.04174 7500. 1.07704 1.06515 1.04421 8000. 1.08105 1.06870 1.04678 8500. 1.08525 1.07237 1.04945 9000. 1.08964 1.07617 1.05220 9500. 1.09423 1.08011 1.05502 10000. 1.09905 1.08421 1.05793 10500. 1.10413 1.08848 1.06092 11000. 1.10949 1.09295 1.06401 11500. 1.11517 1.09761 1.06719 12000. 1.12121 1.10248 1.07048 12500. 1.12764 1.10759 1.07387 13000. 1.13454 1.11296 1.07737 13500. 1.14185 1.11862 1.08099 14000. 1.14953 1.12457 1.08472 14500. 1.15729 1.13076 1.08856 15000. 1.16488 1.13703 1.09246 15500. 1.17188 1.14321 1.09638 16000. 1.17799 1.14909 1.10024 16500. 1.18294 1.15441 1.10400 17000. 1.18667 1.15898 1.10757 17500. 1.18913 1.16260 1.11085 18000. 1.19044 1.16523 1.11376 18500. 1.19075 1.16685 1.11624 19000. 1.19022 1.16748 1.11823 19500. 1.18896 1.16725 1.11969 20000. 1.18704 1.16630 1.12059 20500. 1.18456 1.16474 1.12092 21000. 1.18160 1.16267 1.12073 21500. 1.17823 1.16018 1.12003 22000. 1.17448 1.15733 1.11887 22500. 1.17044 1.15418 1.11730 23000. 1.16614 1.15078 1.11534 23500. 1.16167 1.14715 1.11307 24000. 1.15686 1.14334 1.11052 24500. 1.15206 1.13939 1.10775 25000. 1.14725 1.13533 1.10480 25500. 1.14241 1.13103 1.10169 26000. 1.13756 1.12674 1.09846 26500. 1.13272 1.12244 1.09513 27000. 1.12787 1.11815 1.09172 27500. 1.12303 1.11385 1.08824 28000. 1.11814 1.10959 1.08471 28500. 1.11324 1.10532 1.08115 29000. 1.10835 1.10106 1.07757 30000. 1.09856 1.09253 1.07020 32500. 1.07367 1.07112 1.05206 35000. 1.04831 1.04964 1.03426 37500. 1.02251 1.02808 1.01668 40000. 0.99631 1.00647 0.99936 42500. 0.96978 0.98485 0.98231 45000. 0.94305 0.96327 0.96557 47500. 0.91629 0.94182 0.94917 50000. 0.88973 0.92060 0.93316 52500. 0.86362 0.89973 0.91757 55000. 0.83826 0.87936 0.90246 57500. 0.81399 0.85962 0.88785 60000. 0.79112 0.84068 0.87381 62500. 0.76996 0.82267 0.86037 65000. 0.75074 0.80574 0.84756 67500. 0.73363 0.79000 0.83543 70000. 0.71867 0.77554 0.82400
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-25 Table B.24 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.429 1.419 1.400 100. 1.428 1.419 1.398 500. 1.422 1.414 1.393 1000. 1.415 1.408 1.389 1500. 1.407 1.401 1.383 2000. 1.398 1.393 1.378 2500. 1.389 1.385 1.372 3000. 1.380 1.377 1.366 3500. 1.370 1.369 1.360 4000. 1.360 1.361 1.355 4500. 1.349 1.354 1.349 5000. 1.340 1.347 1.343 5500. 1.332 1.339 1.337 6000. 1.324 1.332 1.331 6500. 1.316 1.324 1.325 7000. 1.307 1.316 1.318 7500. 1.299 1.309 1.312 8000. 1.290 1.301 1.306 8500. 1.281 1.293 1.300 9000. 1.272 1.285 1.294 9500. 1.263 1.277 1.288 10000. 1.254 1.269 1.283 10500. 1.245 1.261 1.277 11000. 1.236 1.253 1.272 11500. 1.226 1.244 1.267 12000. 1.216 1.236 1.261 12500. 1.207 1.228 1.256 13000. 1.197 1.219 1.250 13500. 1.187 1.211 1.245 14000. 1.176 1.202 1.239 14500. 1.166 1.194 1.234 15000. 1.156 1.185 1.228 15500. 1.147 1.177 1.223 16000. 1.139 1.169 1.217 16500. 1.132 1.162 1.210 17000. 1.125 1.154 1.204 17500. 1.119 1.147 1.198 18000. 1.114 1.141 1.191 18500. 1.110 1.136 1.185 19000. 1.105 1.131 1.178 19500. 1.101 1.127 1.172 20000. 1.097 1.123 1.166 20500. 1.094 1.119 1.161 21000. 1.090 1.115 1.156 21500. 1.087 1.112 1.152 22000. 1.085 1.109 1.147 22500. 1.082 1.106 1.144 23000. 1.080 1.103 1.140 23500. 1.078 1.101 1.137 24000. 1.076 1.098 1.134 24500. 1.074 1.096 1.132 25000. 1.072 1.094 1.129 25500. 1.070 1.092 1.127 26000. 1.068 1.090 1.125 26500. 1.066 1.088 1.123 27000. 1.064 1.086 1.121 27500. 1.062 1.084 1.119 28000. 1.060 1.082 1.117 28500. 1.058 1.080 1.115 29000. 1.056 1.078 1.113 30000. 1.052 1.074 1.110 32500. 1.045 1.064 1.101 35000. 1.042 1.054 1.093 37500. 1.041 1.045 1.085 40000. 1.047 1.038 1.077 42500. 1.052 1.034 1.070 45000. 1.057 1.032 1.063 47500. 1.060 1.033 1.056 50000. 1.062 1.037 1.052 52500. 1.064 1.040 1.048 55000. 1.063 1.043 1.045 57500. 1.061 1.044 1.046 60000. 1.057 1.045 1.047 62500. 1.052 1.044 1.050 65000. 1.046 1.042 1.054 67500. 1.039 1.039 1.065 70000. 1.036 1.036 1.076
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-26 Table B.25 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.05327 1.03972 1.02116 100. 1.02755 1.01559 0.99945 500. 1.02472 1.01364 0.99843 1000. 1.02558 1.01521 1.00052 1500. 1.02789 1.01805 1.00353 2000. 1.03061 1.02122 1.00674 2500. 1.03340 1.02438 1.00985 3000. 1.03625 1.02749 1.01279 3500. 1.03919 1.03060 1.01562 4000. 1.04226 1.03377 1.01838 4500. 1.04548 1.03701 1.02114 5000. 1.04890 1.04036 1.02390 5500. 1.05255 1.04386 1.02669 6000. 1.05649 1.04757 1.02956 6500. 1.06072 1.05150 1.03255 7000. 1.06521 1.05563 1.03565 7500. 1.06994 1.05993 1.03887 8000. 1.07488 1.06439 1.04219 8500. 1.08006 1.06898 1.04560 9000. 1.08549 1.07375 1.04910 9500. 1.09122 1.07871 1.05269 10000. 1.09727 1.08388 1.05641 10500. 1.10368 1.08928 1.06023 11000. 1.11049 1.09492 1.06417 11500. 1.11777 1.10083 1.06823 12000. 1.12557 1.10706 1.07241 12500. 1.13395 1.11363 1.07672 13000. 1.14274 1.12055 1.08116 13500. 1.15165 1.12776 1.08571 14000. 1.16027 1.13507 1.09033 14500. 1.16812 1.14221 1.09493 15000. 1.17481 1.14897 1.09945 15500. 1.18014 1.15502 1.10380 16000. 1.18404 1.16014 1.10790 16500. 1.18658 1.16413 1.11165 17000. 1.18790 1.16695 1.11496 17500. 1.18826 1.16860 1.11779 18000. 1.18782 1.16920 1.12009 18500. 1.18670 1.16893 1.12177 19000. 1.18494 1.16795 1.12283 19500. 1.18259 1.16638 1.12327 20000. 1.17971 1.16430 1.12312 20500. 1.17640 1.16179 1.12245 21000. 1.17269 1.15890 1.12128 21500. 1.16863 1.15570 1.11967 22000. 1.16427 1.15224 1.11766 22500. 1.15967 1.14854 1.11532 23000. 1.15461 1.14463 1.11269 23500. 1.14955 1.14055 1.10983 24000. 1.14448 1.13634 1.10680 24500. 1.13942 1.13204 1.10361 25000. 1.13436 1.12756 1.10029 25500. 1.12924 1.12303 1.09687 26000. 1.12412 1.11851 1.09336 26500. 1.11901 1.11398 1.08978 27000. 1.11389 1.10946 1.08614 27500. 1.10877 1.10493 1.08247 28000. 1.10355 1.10044 1.07878 30000. 1.08267 1.08250 1.06364 32500. 1.05606 1.05998 1.04515 35000. 1.02895 1.03738 1.02693 37500. 1.00140 1.01469 1.00897 40000. 0.97348 0.99198 0.99131 42500. 0.94534 0.96932 0.97395 45000. 0.91718 0.94679 0.95696 47500. 0.88926 0.92450 0.94038 50000. 0.86189 0.90260 0.92425 52500. 0.83541 0.88125 0.90862 55000. 0.81020 0.86062 0.89355 57500. 0.78661 0.84088 0.87906 60000. 0.76498 0.82221 0.86522 62500. 0.74555 0.80475 0.85205 65000. 0.72845 0.78862 0.83960 67500. 0.71371 0.77392 0.82791 70000. 0.70123 0.76068 0.81697
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-27 Table B.26 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.399 1.404 1.398 100. 1.398 1.403 1.397 500. 1.391 1.397 1.394 1000. 1.383 1.391 1.391 1500. 1.373 1.383 1.386 2000. 1.362 1.373 1.380 2500. 1.351 1.364 1.373 3000. 1.339 1.353 1.366 3500. 1.326 1.343 1.359 4000. 1.314 1.332 1.351 4500. 1.307 1.321 1.343 5000. 1.300 1.309 1.335 5500. 1.293 1.298 1.326 6000. 1.286 1.286 1.318 6500. 1.278 1.274 1.309 7000. 1.271 1.262 1.300 7500. 1.263 1.250 1.291 8000. 1.255 1.238 1.282 8500. 1.248 1.226 1.273 9000. 1.240 1.214 1.264 9500. 1.232 1.202 1.255 10000. 1.223 1.190 1.246 10500. 1.215 1.179 1.236 11000. 1.207 1.171 1.227 11500. 1.198 1.165 1.218 12000. 1.190 1.159 1.209 12500. 1.181 1.154 1.199 13000. 1.172 1.148 1.190 13500. 1.163 1.142 1.181 14000. 1.154 1.135 1.172 14500. 1.145 1.129 1.162 15000. 1.136 1.122 1.153 15500. 1.139 1.116 1.143 16000. 1.138 1.109 1.134 16500. 1.135 1.103 1.125 17000. 1.132 1.098 1.116 17500. 1.131 1.092 1.107 18000. 1.129 1.088 1.099 18500. 1.126 1.084 1.094 19000. 1.124 1.080 1.089 19500. 1.121 1.077 1.084 20000. 1.119 1.075 1.084 20500. 1.117 1.073 1.084 21000. 1.115 1.072 1.083 21500. 1.112 1.072 1.083 22000. 1.110 1.070 1.082 22500. 1.108 1.069 1.082 23000. 1.106 1.068 1.082 23500. 1.103 1.067 1.081 24000. 1.101 1.066 1.081 24500. 1.098 1.065 1.080 25000. 1.096 1.063 1.079 25500. 1.094 1.062 1.079 26000. 1.091 1.061 1.078 26500. 1.089 1.061 1.077 27000. 1.086 1.060 1.077 27500. 1.084 1.059 1.076 28000. 1.082 1.059 1.075 30000. 1.072 1.058 1.072 32500. 1.072 1.057 1.069 35000. 1.076 1.056 1.066 37500. 1.080 1.055 1.063 40000. 1.082 1.055 1.061 42500. 1.086 1.059 1.059 45000. 1.089 1.062 1.057 47500. 1.090 1.065 1.056 50000. 1.089 1.067 1.056 52500. 1.087 1.068 1.055 55000. 1.083 1.067 1.056 57500. 1.076 1.065 1.057 60000. 1.068 1.063 1.058 62500. 1.059 1.059 1.059 65000. 1.050 1.054 1.064 67500. 1.044 1.048 1.074 70000. 1.052 1.050 1.085
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-28 Table B.27 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.07383 1.06337 1.04873 100. 1.04802 1.03909 1.02678 500. 1.04687 1.03868 1.02704 1000. 1.05030 1.04261 1.03100 1500. 1.05540 1.04801 1.03602 2000. 1.06093 1.05372 1.04120 2500. 1.06663 1.05949 1.04625 3000. 1.07259 1.06535 1.05120 3500. 1.07890 1.07139 1.05613 4000. 1.08567 1.07772 1.06112 4500. 1.09293 1.08438 1.06624 5000. 1.10068 1.09137 1.07151 5500. 1.10889 1.09867 1.07693 6000. 1.11756 1.10627 1.08249 6500. 1.12678 1.11420 1.08820 7000. 1.13664 1.12253 1.09409 7500. 1.14723 1.13130 1.10018 8000. 1.15851 1.14051 1.10649 8500. 1.17044 1.15014 1.11300 9000. 1.18276 1.16012 1.11966 9500. 1.19493 1.17026 1.12642 10000. 1.20636 1.18023 1.13316 10500. 1.21635 1.18957 1.13973 11000. 1.22453 1.19788 1.14599 11500. 1.23073 1.20485 1.15176 12000. 1.23499 1.21028 1.15689 12500. 1.23753 1.21409 1.16126 13000. 1.23865 1.21635 1.16476 13500. 1.23853 1.21724 1.16735 14000. 1.23738 1.21699 1.16902 14500. 1.23535 1.21579 1.16982 15000. 1.23261 1.21384 1.16980 15500. 1.22929 1.21129 1.16904 16000. 1.22550 1.20826 1.16763 16500. 1.22135 1.20485 1.16566 17000. 1.21693 1.20114 1.16323 17500. 1.21233 1.19719 1.16045 18000. 1.20759 1.19306 1.15738 18500. 1.20258 1.18881 1.15410 19000. 1.19757 1.18446 1.15064 19500. 1.19257 1.18005 1.14704 20000. 1.18756 1.17552 1.14335 20500. 1.18256 1.17097 1.13957 21000. 1.17757 1.16641 1.13575 21500. 1.17257 1.16186 1.13189 22000. 1.16758 1.15730 1.12800 22500. 1.16258 1.15275 1.12411 25000. 1.13728 1.13027 1.10444 27500. 1.11150 1.10774 1.08526 30000. 1.08522 1.08512 1.06636 32500. 1.05842 1.06241 1.04771 35000. 1.03111 1.03961 1.02931 37500. 1.00333 1.01672 1.01118 40000. 0.97520 0.99381 0.99334 42500. 0.94685 0.97095 0.97582 45000. 0.91849 0.94823 0.95867 47500. 0.89040 0.92577 0.94194 50000. 0.86288 0.90371 0.92567 52500. 0.83630 0.88224 0.90993 55000. 0.81103 0.86151 0.89476 57500. 0.78745 0.84172 0.88019 60000. 0.76587 0.82302 0.86628 62500. 0.74653 0.80558 0.85307 65000. 0.72956 0.78950 0.84061 67500. 0.71497 0.77487 0.82890 70000. 0.70264 0.76174 0.81799
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-29 Table B.28 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.378 1.383 1.376 100. 1.376 1.381 1.375 500. 1.368 1.374 1.371 1000. 1.357 1.365 1.366 1500. 1.345 1.355 1.360 2000. 1.331 1.344 1.352 2500. 1.317 1.332 1.344 3000. 1.305 1.319 1.335 3500. 1.297 1.307 1.326 4000. 1.289 1.293 1.317 4500. 1.280 1.280 1.307 5000. 1.271 1.266 1.297 5500. 1.262 1.253 1.287 6000. 1.253 1.238 1.277 6500. 1.243 1.224 1.267 7000. 1.233 1.210 1.257 7500. 1.223 1.196 1.246 8000. 1.213 1.181 1.235 8500. 1.202 1.166 1.225 9000. 1.192 1.156 1.214 9500. 1.181 1.148 1.203 10000. 1.170 1.141 1.192 10500. 1.160 1.133 1.181 11000. 1.151 1.125 1.170 11500. 1.142 1.118 1.159 12000. 1.137 1.112 1.149 12500. 1.135 1.106 1.139 13000. 1.132 1.100 1.130 13500. 1.128 1.096 1.121 14000. 1.127 1.092 1.114 14500. 1.125 1.088 1.106 15000. 1.123 1.086 1.100 15500. 1.121 1.085 1.094 16000. 1.119 1.084 1.091 16500. 1.117 1.083 1.089 17000. 1.114 1.082 1.088 17500. 1.112 1.081 1.088 18000. 1.110 1.079 1.087 18500. 1.108 1.078 1.086 19000. 1.106 1.076 1.086 19500. 1.104 1.075 1.085 20000. 1.102 1.073 1.084 20500. 1.100 1.071 1.084 21000. 1.098 1.070 1.083 21500. 1.095 1.068 1.082 22000. 1.093 1.067 1.081 22500. 1.091 1.065 1.081 25000. 1.081 1.058 1.077 27500. 1.070 1.055 1.073 30000. 1.061 1.054 1.069 32500. 1.060 1.053 1.065 35000. 1.064 1.053 1.062 37500. 1.067 1.052 1.059 40000. 1.070 1.051 1.057 42500. 1.072 1.049 1.055 45000. 1.074 1.052 1.054 47500. 1.075 1.054 1.053 50000. 1.075 1.056 1.052 52500. 1.073 1.056 1.052 55000. 1.069 1.056 1.052 57500. 1.063 1.055 1.053 60000. 1.056 1.052 1.055 62500. 1.048 1.048 1.056 65000. 1.039 1.044 1.064 67500. 1.041 1.039 1.074 70000. 1.051 1.050 1.085
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-30 Table B.29 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.08960 1.07180 1.04997 100. 1.06350 1.04749 1.02821 500. 1.05991 1.04471 1.02626 1000. 1.05951 1.04491 1.02688 1500. 1.06040 1.04621 1.02832 2000. 1.06171 1.04785 1.02996 2500. 1.06312 1.04955 1.03158 3000. 1.06451 1.05117 1.03309 3500. 1.06592 1.05272 1.03449 4000. 1.06737 1.05426 1.03580 4500. 1.06888 1.05581 1.03706 5000. 1.07047 1.05739 1.03831 5500. 1.07214 1.05902 1.03955 6000. 1.07393 1.06071 1.04082 6500. 1.07587 1.06249 1.04213 7000. 1.07798 1.06439 1.04350 7500. 1.08027 1.06643 1.04495 8000. 1.08274 1.06860 1.04648 8500. 1.08535 1.07090 1.04811 9000. 1.08810 1.07330 1.04981 9500. 1.09097 1.07580 1.05158 10000. 1.09398 1.07840 1.05340 10500. 1.09712 1.08110 1.05527 11000. 1.10041 1.08392 1.05721 11500. 1.10387 1.08685 1.05920 12000. 1.10750 1.08990 1.06125 12500. 1.11133 1.09308 1.06337 13000. 1.11537 1.09640 1.06556 13500. 1.11965 1.09987 1.06782 14000. 1.12421 1.10350 1.07015 14500. 1.12910 1.10732 1.07257 15000. 1.13435 1.11134 1.07507 15500. 1.13997 1.11557 1.07765 16000. 1.14589 1.11996 1.08029 16500. 1.15192 1.12444 1.08297 17000. 1.15780 1.12892 1.08562 17500. 1.16327 1.13327 1.08822 18000. 1.16809 1.13735 1.09071 18500. 1.17196 1.14102 1.09306 19000. 1.17474 1.14413 1.09523 19500. 1.17634 1.14657 1.09715 20000. 1.17682 1.14828 1.09880 20500. 1.17633 1.14920 1.10016 21000. 1.17506 1.14937 1.10120 21500. 1.17313 1.14884 1.10188 22000. 1.17066 1.14769 1.10219 22500. 1.16774 1.14597 1.10212 23000. 1.16444 1.14376 1.10165 23500. 1.16081 1.14116 1.10081 24000. 1.15691 1.13823 1.09964 24500. 1.15276 1.13505 1.09813 25000. 1.14843 1.13164 1.09631 25500. 1.14375 1.12804 1.09420 26000. 1.13907 1.12430 1.09183 26500. 1.13440 1.12043 1.08924 27000. 1.12972 1.11648 1.08646 27500. 1.12504 1.11237 1.08353 28000. 1.12035 1.10822 1.08048 28500. 1.11566 1.10407 1.07733 29000. 1.11097 1.09993 1.07409 29500. 1.10628 1.09578 1.07078 30000. 1.10159 1.09163 1.06743 30500. 1.09684 1.08753 1.06404 31000. 1.09209 1.08343 1.06062 31500. 1.08735 1.07933 1.05719 32500. 1.07785 1.07113 1.05017 35000. 1.05382 1.05065 1.03295 37500. 1.02951 1.03023 1.01610 40000. 1.00496 1.00986 0.99956 42500. 0.98023 0.98960 0.98336 45000. 0.95542 0.96949 0.96751 47500. 0.93066 0.94959 0.95205 50000. 0.90610 0.92997 0.93701 52500. 0.88194 0.91073 0.92242 55000. 0.85842 0.89196 0.90830 57500. 0.83575 0.87377 0.89471 60000. 0.81420 0.85627 0.88165 62500. 0.79399 0.83956 0.86917 65000. 0.77531 0.82374 0.85727 67500. 0.75835 0.80889 0.84599 70000. 0.74318 0.79509 0.83534
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-31 Table B.30 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.491 1.475 1.440 100. 1.490 1.475 1.438 500. 1.484 1.470 1.434 1000. 1.478 1.465 1.429 1500. 1.470 1.458 1.424 2000. 1.461 1.451 1.419 2500. 1.452 1.443 1.413 3000. 1.442 1.435 1.408 3500. 1.432 1.426 1.402 4000. 1.422 1.418 1.397 4500. 1.412 1.409 1.391 5000. 1.401 1.400 1.385 5500. 1.390 1.392 1.380 6000. 1.382 1.384 1.374 6500. 1.374 1.377 1.368 7000. 1.365 1.370 1.362 7500. 1.357 1.362 1.356 8000. 1.349 1.354 1.350 8500. 1.340 1.347 1.344 9000. 1.332 1.339 1.338 9500. 1.323 1.331 1.331 10000. 1.314 1.324 1.325 10500. 1.306 1.316 1.319 11000. 1.297 1.308 1.313 11500. 1.288 1.300 1.307 12000. 1.279 1.292 1.302 12500. 1.270 1.284 1.296 13000. 1.260 1.276 1.291 13500. 1.251 1.268 1.286 14000. 1.242 1.260 1.281 14500. 1.232 1.252 1.276 15000. 1.222 1.244 1.270 15500. 1.213 1.235 1.265 16000. 1.203 1.227 1.260 16500. 1.193 1.219 1.255 17000. 1.183 1.211 1.249 17500. 1.174 1.203 1.243 18000. 1.165 1.195 1.238 18500. 1.157 1.187 1.232 19000. 1.150 1.180 1.225 19500. 1.144 1.173 1.219 20000. 1.138 1.167 1.213 20500. 1.133 1.161 1.206 21000. 1.128 1.155 1.200 21500. 1.123 1.150 1.194 22000. 1.119 1.145 1.188 22500. 1.115 1.141 1.183 23000. 1.111 1.137 1.178 23500. 1.107 1.133 1.173 24000. 1.104 1.129 1.168 24500. 1.101 1.126 1.164 25000. 1.098 1.123 1.160 25500. 1.095 1.120 1.157 26000. 1.092 1.117 1.154 26500. 1.090 1.114 1.151 27000. 1.087 1.111 1.148 27500. 1.084 1.109 1.145 28000. 1.081 1.106 1.142 28500. 1.079 1.104 1.140 29000. 1.076 1.101 1.138 29500. 1.074 1.099 1.135 30000. 1.071 1.096 1.133 30500. 1.070 1.094 1.131 31000. 1.069 1.091 1.129 31500. 1.068 1.089 1.127 32500. 1.066 1.084 1.123 35000. 1.060 1.072 1.114 37500. 1.054 1.060 1.105 40000. 1.052 1.052 1.096 42500. 1.053 1.048 1.088 45000. 1.054 1.044 1.081 47500. 1.057 1.041 1.074 50000. 1.060 1.037 1.068 52500. 1.062 1.036 1.065 55000. 1.062 1.037 1.065 57500. 1.061 1.039 1.065 60000. 1.059 1.040 1.067 62500. 1.055 1.040 1.072 65000. 1.050 1.039 1.082 67500. 1.044 1.037 1.093 70000. 1.047 1.052 1.103
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-32 Table B.31 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.06503 1.04956 1.02975 100. 1.03909 1.02529 1.00792 500. 1.03572 1.02273 1.00620 1000. 1.03560 1.02325 1.00720 1500. 1.03684 1.02495 1.00906 2000. 1.03854 1.02702 1.01116 2500. 1.04034 1.02916 1.01325 3000. 1.04214 1.03122 1.01522 3500. 1.04400 1.03324 1.01708 4000. 1.04592 1.03527 1.01886 4500. 1.04792 1.03733 1.02061 5000. 1.05002 1.03943 1.02235 5500. 1.05224 1.04160 1.02408 6000. 1.05461 1.04385 1.02584 6500. 1.05715 1.04621 1.02765 7000. 1.05990 1.04873 1.02954 7500. 1.06286 1.05140 1.03151 8000. 1.06602 1.05423 1.03360 8500. 1.06935 1.05719 1.03577 9000. 1.07285 1.06028 1.03804 9500. 1.07649 1.06348 1.04038 10000. 1.08030 1.06680 1.04278 10500. 1.08427 1.07025 1.04524 11000. 1.08844 1.07383 1.04778 11500. 1.09282 1.07755 1.05038 12000. 1.09744 1.08143 1.05307 12500. 1.10232 1.08548 1.05583 13000. 1.10751 1.08970 1.05868 13500. 1.11304 1.09412 1.06162 14000. 1.11897 1.09877 1.06466 14500. 1.12535 1.10368 1.06780 15000. 1.13215 1.10887 1.07106 15500. 1.13922 1.11435 1.07442 16000. 1.14635 1.12003 1.07789 16500. 1.15322 1.12577 1.08142 17000. 1.15953 1.13141 1.08495 17500. 1.16501 1.13678 1.08844 18000. 1.16940 1.14163 1.09183 18500. 1.17263 1.14576 1.09506 19000. 1.17469 1.14904 1.09805 19500. 1.17567 1.15141 1.10070 20000. 1.17574 1.15282 1.10298 20500. 1.17505 1.15333 1.10484 21000. 1.17372 1.15302 1.10622 21500. 1.17179 1.15204 1.10711 22000. 1.16933 1.15051 1.10747 22500. 1.16641 1.14851 1.10732 23000. 1.16310 1.14609 1.10672 23500. 1.15943 1.14334 1.10568 24000. 1.15545 1.14029 1.10425 24500. 1.15120 1.13699 1.10245 25000. 1.14674 1.13346 1.10034 25500. 1.14189 1.12974 1.09794 26000. 1.13703 1.12587 1.09531 26500. 1.13218 1.12186 1.09250 27000. 1.12732 1.11777 1.08952 27500. 1.12247 1.11350 1.08642 28000. 1.11759 1.10919 1.08320 28500. 1.11271 1.10488 1.07989 29000. 1.10783 1.10056 1.07650 29500. 1.10295 1.09625 1.07306 30000. 1.09807 1.09194 1.06956 30500. 1.09310 1.08767 1.06604 31000. 1.08813 1.08340 1.06249 32500. 1.07322 1.07059 1.05156 35000. 1.04793 1.04917 1.03374 37500. 1.02220 1.02767 1.01621 40000. 0.99606 1.00612 0.99894 42500. 0.96960 0.98455 0.98194 45000. 0.94293 0.96303 0.96524 47500. 0.91623 0.94164 0.94888 50000. 0.88972 0.92047 0.93291 52500. 0.86364 0.89965 0.91735 55000. 0.83831 0.87930 0.90226 57500. 0.81403 0.85959 0.88769 60000. 0.79115 0.84065 0.87366 62500. 0.76995 0.82264 0.86023 65000. 0.75068 0.80569 0.84742 67500. 0.73350 0.78992 0.83529 70000. 0.71847 0.77542 0.82385
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-33 Table B.32 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.433 1.423 1.404 100. 1.432 1.423 1.401 500. 1.427 1.418 1.397 1000. 1.420 1.413 1.393 1500. 1.413 1.406 1.388 2000. 1.404 1.399 1.382 2500. 1.396 1.392 1.377 3000. 1.387 1.384 1.371 3500. 1.377 1.376 1.366 4000. 1.368 1.368 1.360 4500. 1.358 1.361 1.355 5000. 1.348 1.354 1.349 5500. 1.340 1.347 1.343 6000. 1.333 1.340 1.338 6500. 1.325 1.333 1.332 7000. 1.317 1.325 1.326 7500. 1.309 1.318 1.320 8000. 1.301 1.310 1.314 8500. 1.293 1.303 1.308 9000. 1.284 1.295 1.302 9500. 1.276 1.288 1.296 10000. 1.267 1.280 1.291 10500. 1.259 1.273 1.286 11000. 1.250 1.265 1.280 11500. 1.241 1.257 1.275 12000. 1.232 1.249 1.270 12500. 1.223 1.242 1.265 13000. 1.214 1.234 1.259 13500. 1.205 1.226 1.254 14000. 1.196 1.218 1.249 14500. 1.186 1.210 1.244 15000. 1.176 1.202 1.239 15500. 1.166 1.193 1.233 16000. 1.157 1.185 1.228 16500. 1.147 1.178 1.223 17000. 1.139 1.171 1.217 17500. 1.131 1.164 1.211 18000. 1.124 1.156 1.205 18500. 1.117 1.149 1.199 19000. 1.112 1.142 1.193 19500. 1.107 1.135 1.186 20000. 1.102 1.129 1.180 20500. 1.098 1.124 1.174 21000. 1.094 1.120 1.168 21500. 1.090 1.116 1.162 22000. 1.086 1.112 1.157 22500. 1.083 1.108 1.152 23000. 1.080 1.105 1.147 23500. 1.077 1.101 1.143 24000. 1.074 1.098 1.139 24500. 1.072 1.096 1.135 25000. 1.070 1.093 1.132 25500. 1.068 1.090 1.129 26000. 1.066 1.088 1.126 26500. 1.063 1.086 1.124 27000. 1.061 1.084 1.121 27500. 1.059 1.082 1.119 28000. 1.057 1.080 1.117 28500. 1.055 1.078 1.115 29000. 1.053 1.076 1.113 29500. 1.051 1.074 1.111 30000. 1.049 1.072 1.109 30500. 1.048 1.070 1.107 31000. 1.048 1.068 1.105 32500. 1.046 1.062 1.100 35000. 1.044 1.053 1.092 37500. 1.045 1.044 1.084 40000. 1.051 1.038 1.076 42500. 1.056 1.035 1.069 45000. 1.061 1.033 1.062 47500. 1.065 1.036 1.056 50000. 1.067 1.040 1.052 52500. 1.068 1.044 1.048 55000. 1.068 1.046 1.045 57500. 1.065 1.048 1.047 60000. 1.062 1.048 1.048 62500. 1.056 1.047 1.051 65000. 1.050 1.045 1.054 67500. 1.043 1.042 1.065 70000. 1.036 1.038 1.076
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-34 Table B.33 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.05139 1.03692 1.01740 100. 1.02563 1.01278 0.99569 500. 1.02244 1.01047 0.99434 1000. 1.02271 1.01149 0.99593 1500. 1.02438 1.01371 0.99838 2000. 1.02648 1.01628 1.00105 2500. 1.02865 1.01888 1.00366 3000. 1.03085 1.02140 1.00612 3500. 1.03312 1.02390 1.00845 4000. 1.03547 1.02643 1.01071 4500. 1.03794 1.02901 1.01295 5000. 1.04053 1.03165 1.01519 5500. 1.04328 1.03437 1.01743 6000. 1.04623 1.03723 1.01971 6500. 1.04941 1.04025 1.02205 7000. 1.05284 1.04346 1.02450 7500. 1.05652 1.04687 1.02707 8000. 1.06041 1.05043 1.02975 8500. 1.06449 1.05413 1.03252 9000. 1.06874 1.05795 1.03537 9500. 1.07319 1.06190 1.03830 10000. 1.07784 1.06600 1.04130 10500. 1.08273 1.07026 1.04437 11000. 1.08788 1.07469 1.04754 11500. 1.09332 1.07932 1.05079 12000. 1.09912 1.08415 1.05414 12500. 1.10530 1.08920 1.05759 13000. 1.11195 1.09450 1.06114 13500. 1.11910 1.10011 1.06481 14000. 1.12675 1.10605 1.06860 14500. 1.13471 1.11234 1.07252 15000. 1.14277 1.11889 1.07654 15500. 1.15049 1.12550 1.08064 16000. 1.15743 1.13198 1.08472 16500. 1.16332 1.13812 1.08875 17000. 1.16800 1.14366 1.09266 17500. 1.17140 1.14834 1.09637 18000. 1.17359 1.15199 1.09980 18500. 1.17468 1.15458 1.10286 19000. 1.17489 1.15610 1.10551 19500. 1.17437 1.15664 1.10771 20000. 1.17323 1.15633 1.10939 20500. 1.17150 1.15536 1.11051 21000. 1.16922 1.15384 1.11104 21500. 1.16642 1.15185 1.11102 22000. 1.16320 1.14944 1.11050 22500. 1.15961 1.14668 1.10951 23000. 1.15567 1.14361 1.10810 23500. 1.15142 1.14028 1.10629 24000. 1.14690 1.13671 1.10415 24500. 1.14217 1.13293 1.10172 25000. 1.13716 1.12897 1.09904 25500. 1.13201 1.12485 1.09617 26000. 1.12686 1.12061 1.09314 26500. 1.12170 1.11612 1.08997 27000. 1.11655 1.11163 1.08669 27500. 1.11140 1.10714 1.08331 28000. 1.10622 1.10266 1.07985 28500. 1.10104 1.09819 1.07632 29000. 1.09586 1.09371 1.07274 29500. 1.09068 1.08924 1.06912 30000. 1.08550 1.08476 1.06547 32500. 1.05911 1.06239 1.04686 35000. 1.03220 1.03993 1.02871 37500. 1.00483 1.01738 1.01081 40000. 0.97707 0.99478 0.99320 42500. 0.94906 0.97220 0.97589 45000. 0.92098 0.94973 0.95892 47500. 0.89308 0.92748 0.94235 50000. 0.86565 0.90557 0.92620 52500. 0.83904 0.88417 0.91055 55000. 0.81360 0.86344 0.89543 57500. 0.78972 0.84356 0.88089 60000. 0.76773 0.82471 0.86696 62500. 0.74788 0.80702 0.85369 65000. 0.73035 0.79063 0.84113 67500. 0.71517 0.77565 0.82930 70000. 0.70227 0.76212 0.81823
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-35 Table B.34 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.397 1.401 1.394 100. 1.396 1.400 1.394 500. 1.389 1.395 1.391 1000. 1.382 1.389 1.389 1500. 1.373 1.382 1.384 2000. 1.363 1.373 1.379 2500. 1.352 1.364 1.373 3000. 1.341 1.355 1.366 3500. 1.329 1.345 1.359 4000. 1.318 1.334 1.352 4500. 1.306 1.324 1.345 5000. 1.300 1.313 1.337 5500. 1.293 1.302 1.329 6000. 1.287 1.291 1.321 6500. 1.280 1.280 1.313 7000. 1.273 1.269 1.304 7500. 1.266 1.258 1.296 8000. 1.259 1.246 1.288 8500. 1.252 1.235 1.279 9000. 1.244 1.223 1.270 9500. 1.237 1.212 1.262 10000. 1.229 1.200 1.253 10500. 1.222 1.189 1.244 11000. 1.214 1.178 1.235 11500. 1.206 1.170 1.226 12000. 1.198 1.164 1.218 12500. 1.190 1.159 1.209 13000. 1.182 1.154 1.200 13500. 1.174 1.148 1.192 14000. 1.166 1.143 1.183 14500. 1.157 1.137 1.174 15000. 1.149 1.131 1.166 15500. 1.140 1.125 1.157 16000. 1.132 1.119 1.148 16500. 1.133 1.113 1.139 17000. 1.134 1.107 1.130 17500. 1.132 1.101 1.122 18000. 1.128 1.095 1.117 18500. 1.128 1.090 1.111 19000. 1.127 1.084 1.106 19500. 1.124 1.080 1.101 20000. 1.122 1.076 1.096 20500. 1.119 1.074 1.091 21000. 1.116 1.072 1.087 21500. 1.114 1.071 1.082 22000. 1.112 1.070 1.079 22500. 1.109 1.069 1.079 23000. 1.107 1.068 1.078 23500. 1.105 1.067 1.078 24000. 1.102 1.066 1.077 24500. 1.100 1.065 1.077 25000. 1.097 1.063 1.077 25500. 1.095 1.062 1.076 26000. 1.092 1.061 1.076 26500. 1.090 1.060 1.075 27000. 1.087 1.058 1.074 27500. 1.085 1.057 1.074 28000. 1.083 1.057 1.073 28500. 1.080 1.056 1.072 29000. 1.078 1.056 1.072 29500. 1.075 1.055 1.071 30000. 1.073 1.055 1.070 32500. 1.072 1.054 1.067 35000. 1.076 1.053 1.064 37500. 1.079 1.052 1.061 40000. 1.082 1.054 1.059 42500. 1.086 1.058 1.057 45000. 1.089 1.062 1.055 47500. 1.090 1.065 1.054 50000. 1.090 1.067 1.054 52500. 1.088 1.068 1.054 55000. 1.084 1.068 1.054 57500. 1.078 1.066 1.055 60000. 1.071 1.064 1.057 62500. 1.062 1.060 1.058 65000. 1.053 1.056 1.061 67500. 1.043 1.050 1.072 70000. 1.051 1.047 1.083
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-36 Table B.35 [ ] Hot Uncontrolled k Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.07609 1.06566 1.05106 100. 1.05022 1.04133 1.02907 500. 1.04902 1.04085 1.02925 1000. 1.05236 1.04468 1.03310 1500. 1.05739 1.04998 1.03802 2000. 1.06284 1.05561 1.04310 2500. 1.06848 1.06130 1.04807 3000. 1.07437 1.06708 1.05293 3500. 1.08060 1.07304 1.05777 4000. 1.08728 1.07927 1.06267 4500. 1.09445 1.08583 1.06769 5000. 1.10211 1.09273 1.07286 5500. 1.11022 1.09992 1.07818 6000. 1.11878 1.10742 1.08364 6500. 1.12789 1.11523 1.08924 7000. 1.13763 1.12345 1.09503 7500. 1.14806 1.13209 1.10101 8000. 1.15921 1.14117 1.10721 8500. 1.17100 1.15067 1.11360 9000. 1.18321 1.16053 1.12016 9500. 1.19533 1.17059 1.12683 10000. 1.20676 1.18053 1.13351 10500. 1.21683 1.18990 1.14005 11000. 1.22514 1.19830 1.14631 11500. 1.23149 1.20539 1.15211 12000. 1.23593 1.21097 1.15730 12500. 1.23866 1.21495 1.16176 13000. 1.23993 1.21738 1.16536 13500. 1.23996 1.21841 1.16805 14000. 1.23891 1.21828 1.16984 14500. 1.23698 1.21718 1.17074 15000. 1.23432 1.21531 1.17083 15500. 1.23106 1.21283 1.17015 16000. 1.22732 1.20986 1.16882 16500. 1.22322 1.20649 1.16692 17000. 1.21884 1.20282 1.16455 17500. 1.21427 1.19890 1.16181 18000. 1.20956 1.19480 1.15879 18500. 1.20458 1.19057 1.15553 19000. 1.19960 1.18624 1.15210 19500. 1.19461 1.18186 1.14853 20000. 1.18963 1.17734 1.14485 20500. 1.18465 1.17280 1.14110 21000. 1.17968 1.16826 1.13729 21500. 1.17470 1.16373 1.13344 22000. 1.16973 1.15919 1.12957 22500. 1.16475 1.15465 1.12568 25000. 1.13957 1.13224 1.10606 27500. 1.11390 1.10978 1.08691 30000. 1.08773 1.08724 1.06804 32500. 1.06104 1.06460 1.04940 35000. 1.03383 1.04185 1.03102 37500. 1.00614 1.01902 1.01290 40000. 0.97807 0.99615 0.99506 42500. 0.94977 0.97330 0.97754 45000. 0.92142 0.95059 0.96038 47500. 0.89330 0.92811 0.94362 50000. 0.86571 0.90602 0.92732 52500. 0.83901 0.88448 0.91153 55000. 0.81357 0.86366 0.89630 57500. 0.78978 0.84375 0.88167 60000. 0.76795 0.82491 0.86769 62500. 0.74834 0.80731 0.85440 65000. 0.73109 0.79106 0.84185 67500. 0.71623 0.77625 0.83006 70000. 0.70365 0.76294 0.81904
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page B-37 Table B.36 [ ] Hot Uncontrolled LPF Exposure 0.00 Void 0.40 Void 0.80 Void MWd/MTU History History History
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| : 0. 1.373 1.376 1.369 100. 1.371 1.375 1.368 500. 1.363 1.368 1.364 1000. 1.352 1.359 1.360 1500. 1.340 1.349 1.353 2000. 1.327 1.338 1.346 2500. 1.313 1.326 1.338 3000. 1.300 1.314 1.329 3500. 1.292 1.302 1.321 4000. 1.284 1.289 1.312 4500. 1.275 1.276 1.302 5000. 1.267 1.262 1.293 5500. 1.258 1.248 1.283 6000. 1.248 1.235 1.273 6500. 1.239 1.221 1.263 7000. 1.229 1.206 1.252 7500. 1.219 1.192 1.242 8000. 1.209 1.178 1.232 8500. 1.199 1.163 1.221 9000. 1.188 1.151 1.211 9500. 1.178 1.144 1.200 10000. 1.167 1.137 1.189 10500. 1.157 1.129 1.178 11000. 1.147 1.122 1.167 11500. 1.138 1.115 1.157 12000. 1.135 1.108 1.146 12500. 1.132 1.102 1.137 13000. 1.129 1.097 1.127 13500. 1.126 1.092 1.119 14000. 1.124 1.088 1.111 14500. 1.122 1.085 1.104 15000. 1.120 1.084 1.097 15500. 1.118 1.083 1.092 16000. 1.116 1.082 1.088 16500. 1.114 1.081 1.087 17000. 1.112 1.080 1.086 17500. 1.110 1.078 1.086 18000. 1.108 1.077 1.085 18500. 1.106 1.076 1.084 19000. 1.104 1.074 1.084 19500. 1.101 1.072 1.083 20000. 1.099 1.071 1.082 20500. 1.097 1.069 1.082 21000. 1.095 1.068 1.081 21500. 1.093 1.066 1.080 22000. 1.091 1.065 1.079 22500. 1.089 1.063 1.079 25000. 1.078 1.055 1.075 27500. 1.068 1.053 1.071 30000. 1.058 1.051 1.067 32500. 1.057 1.050 1.063 35000. 1.061 1.050 1.060 37500. 1.064 1.049 1.057 40000. 1.066 1.048 1.055 42500. 1.068 1.047 1.053 45000. 1.071 1.049 1.052 47500. 1.072 1.051 1.051 50000. 1.072 1.053 1.050 52500. 1.070 1.054 1.050 55000. 1.067 1.054 1.051 57500. 1.061 1.053 1.052 60000. 1.055 1.051 1.053 62500. 1.047 1.047 1.055 65000. 1.038 1.043 1.062 67500. 1.040 1.038 1.073 70000. 1.049 1.048 1.083
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-1 Appendix C Enriched Lattice Isotopic Data Tables The results in this appendix are based on hot operating and equilibrium xenon conditions.
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-2 Table C.1 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-3 Table C.2 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-4 Table C.3 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-5 Table C.4 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-6 Table C.5 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-7 Table C.6 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-8 Table C.7 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-9 Table C.8 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-10 Table C.9 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-11 Table C.10 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-12 Table C.11 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-13 Table C.12 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-14 Table C.13 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-15 Table C.14 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-16 Table C.15 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-17 Table C.16 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-18 Table C.17 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-19 Table C.18 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-20 Table C.19 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-21 Table C.20 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-22 Table C.21 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-23 Table C.22 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-24 Table C.23 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-25 Table C.24 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-26 Table C.25 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-27 Table C.26 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-28 Table C.27 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-29 Table C.28 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-30 Table C.29 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-31 Table C.30 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-32 Table C.31 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-33 Table C.32 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-34 Table C.33 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-35 Table C.34 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-36 Table C.35 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-37 Table C.36 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-38 Table C.37 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-39 Table C.38 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-40 Table C.39 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-41 Table C.40 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-42 Table C.41 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-43 Table C.42 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-44 Table C.43 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-45 Table C.44 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-46 Table C.45 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-47 Table C.46 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-48 Table C.47 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-49 Table C.48 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-50 Table C.49 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-51 Table C.50 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-52 Table C.51 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-53 Table C.52 [ ] Exposure-Dependent 0% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-54 Table C.53 [ ] Exposure-Dependent 40% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page C-55 Table C.54 [ ] Exposure-Dependent 80% Void Isotopics (kg/MTU Initial)
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-1 Appendix D Lattice Enrichment Distribution Maps
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-2 Figure D.1 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-3 Figure D.2 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-4 Figure D.3 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-5 Figure D.4 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-6 Figure D.5 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-7 Figure D.6 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-8 Figure D.7 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-9 Figure D.8 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-10 Figure D.9 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-11 Figure D.10 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-12 Figure D.11 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-13 Figure D.12 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-14 Figure D.13 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-15 Figure D.14 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-16 Figure D.15 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-17 Figure D.16 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-18 Figure D.17 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-19 Figure D.18 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-20 Figure D.19 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-21 Figure D.20 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-22 Figure D.21 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-23 Figure D.22 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-24 Figure D.23 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-25 Figure D.24 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-26 Figure D.25 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-27 Figure D.26 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-28 Figure D.27 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-29 Figure D.28 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-30 Figure D.29 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-31 Figure D.30 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-32 Figure D.31 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-33 Figure D.32 [ ] Enrichment Distribution
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| Controlled Document Framatome Inc. ANP-3758NP Revision 1 Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report Page D-34 Figure D.33 [ ] Enrichment Distribution
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| RA-19-0411 Enclosure 9 Affidavits for ANP-3808P, ANP-3791P, ANP-3759P, and ANP-3758P
| |
| | |
| AFFIDAVIT
| |
| : 1. My name is Alan B. Meginnis. I am Manager, Product Licensing, for Framatome Inc. and as such I am authorized to execute this Affidavit.
| |
| : 2. I am familiar with the criteria applied by Framatome to determine whether certain Framatome information is proprietary. I am familiar with the policies established by Framatome to ensure the proper application of these criteria.
| |
| : 3. I am familiar with the Framatome information contained in the report ANP-3808P, Revision 0, "Brunswick Unit 1 Cycle 23 Reload Safety Analysis," dated October 2019 and referred to herein as "Document." Information contained in this Document has been classified by Framatome as proprietary in accordance with the policies established by Framatome for the control and protection of proprietary and confidential information.
| |
| : 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by Framatome and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
| |
| : 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."
| |
| : 6. The following criteria are customarily applied by Framatome to determine whether information should be classified as proprietary:
| |
| (a) The information reveals details of Framatome's research and development plans and programs or their results.
| |
| (b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
| |
| (c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for Framatome.
| |
| (d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for Framatome in product optimization or marketability.
| |
| (e) The information is vital to a competitive advantage held by Framatome, would be helpful to competitors to Framatome, and would likely cause substantial harm to the competitive position of Framatome.
| |
| The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d) and 6(e) above.
| |
| : 7. In accordance with Framatome's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside Framatome only as required and under suitable agreement providing for nondisclosure and limited use of the information.
| |
| : 8. Framatome policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
| |
| : 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
| |
| | |
| /''
| |
| .y
| |
| -1 i;,c~e-1__ .1.:
| |
| Alan Meginnis
| |
| ~
| |
| STATE OF WASHINGTON )
| |
| ) ss.
| |
| COUNTY OF BENTON )
| |
| SUBSCRIBED before me this-'-~-- day o f ( ) ~ k_v::: ,2019.
| |
| \\''""'''''
| |
| ,,,, ~ K Mc ,,,,,
| |
| $' ~? . . . EXP. ,.;**"o** 'J-,.,',
| |
| ,, ~t;>- ..........
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| ~
| |
| ... <:,j.*
| |
| : ~PE
| |
| :;.. NOTAAY pU8LIC
| |
| ,:\
| |
| oiz:
| |
| :o:
| |
| ~
| |
| Susan K. McCoy ~ ~.. !1>1,-;;.:
| |
| ~ -y:*. "a ~ '°
| |
| ,r::f'/0 ~
| |
| NOTARY PUBLIC, STATE OF WP! INGTON ',~ r,t,,.**.~M
| |
| .... . NO*
| |
| . .,,,,,o;:-******sy,.' ..
| |
| .. WP.: ,,,'-''
| |
| 1 **
| |
| MY COMMISSION EXPIRES: 1/14/2020
| |
| | |
| AFFIDAVIT
| |
| : 1. My name is Alan B. Meginnis. I am Manager, Product Licensing, for Framatome Inc. and as such I am authorized to execute this Affidavit.
| |
| : 2. I am familiar with the criteria applied by Framatome to determine whether certain Framatome information is proprietary. I am familiar with the policies established by Framatome to ensure the proper application of these criteria.
| |
| : 3. I am familiar with the Framatome information contained in the report ANP-3791 P, Revision 0, "ATRIUM 11 Fuel Rod Thermal-Mechanical Evaluation for Brunswick Unit 1 Cycle 23," dated October 2019 and referred to herein as "Document." Information contained in this Document has been classified by Framatome as proprietary in accordance with the policies established by Framatome for the control and protection of proprietary and confidential information.
| |
| : 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by Framatome and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
| |
| : 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."
| |
| : 6. The following criteria are customarily applied by Framatome to determine whether information should be classified as proprietary:
| |
| (a) The information reveals details of Framatome's research and development plans and programs or their results.
| |
| (b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
| |
| (c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for Framatome.
| |
| (d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for Framatome in product optimization or marketability.
| |
| (e) The information is vital to a competitive advantage held by Framatome, would be helpful to competitors to Framatome, and would likely cause substantial harm to the competitive position of Framatome.
| |
| The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d) and 6(e) above.
| |
| : 7. In accordance with Framatome's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside Framatome only as required and under suitable agreement providing for nondisclosure and limited use of the information.
| |
| : 8. Framatome policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
| |
| : 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
| |
| | |
| tZfr;_ ~ ~ - - - -
| |
| Alan Meginnis STATE OF WASHINGTON )
| |
| ) ss.
| |
| COUNTY OF BENTON )
| |
| SUBSCRIBED before me this l 7 ~ day of O ~b>> , 2019.
| |
| ,,, N K /t,t ,,,,
| |
| ,,'~f:,~..........cco'.,.,
| |
| .:,'**EXP.***,,,
| |
| :-:,-4.
| |
| to~~* . ,.,. *** ').. ~
| |
| Cl)\ 2
| |
| * ),, NOTARY ~
| |
| PUBLIC
| |
| . r.~ ~
| |
| O i 2 :
| |
| :O=
| |
| NOTARY PUBLIC, STATE OF WASHINGTON
| |
| -:.,,"Y~**"a
| |
| , .. . NO .~,~..**:._,0,,,,,,-~
| |
| ~**. flt,_,
| |
| ~l"- "'
| |
| ,,,,,,,,o;.*******sy,,.°' ~
| |
| MY COMMISSION EXPIRES: 1/14/2020 WA ,,,
| |
| | |
| AFFIDAVIT
| |
| : 1. My name is Alan B. Meginnis. I am Manager, Product Licensing, for Framatome Inc. and as such I am authorized to execute this Affidavit.
| |
| : 2. I am familiar with the criteria applied by Framatome to determine whether certain Framatome information is proprietary. I am familiar with the policies established by Framatome to ensure the proper application of these criteria.
| |
| : 3. I am familiar with the Framatome information contained in the report ANP-3759P, Revision 2, "Brunswick Unit 1 Cycle 23 Fuel Cycle Design Report," dated October 2019 and referred to herein as "Document." Information contained in this Document has been classified by Framatome as proprietary in accordance with the policies established by Framatome for the control and protection of proprietary and confidential information.
| |
| : 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by Framatome and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
| |
| : 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."
| |
| : 6. The following criteria are customarily applied by Framatome to determine whether information should be classified as proprietary:
| |
| (a) The information reveals details of Framatome's research and development plans and programs or their results.
| |
| (b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
| |
| (c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for Framatome.
| |
| (d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for Framatome in product optimization or marketability.
| |
| (e) The information is vital to a competitive advantage held by Framatome, would be helpful to competitors to Framatome, and would likely cause substantial harm to the competitive position of Framatome.
| |
| The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d) and 6(e) above.
| |
| : 7. In accordance with Framatome's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside Framatome only as required and under suitable agreement providing for nondisclosure and limited use of the information.
| |
| : 8. Framatome policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
| |
| : 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
| |
| | |
| Alan Meginnis ?
| |
| STATE OF WASHINGTON )
| |
| ) ss.
| |
| COUNTY OF BENTON )
| |
| SUBSCRIBED before me this
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| Susan K. McCoy . c
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| PUBIJC *0:
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| NOTARY PUBLIC, STATE OF WASHINGTON ,:,~-y;*.~*.}!M.
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| NO* ~!{~ $
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| MY COMMISSION EXPIRES: 1/14/2020
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| | |
| AFFIDAVIT
| |
| : 1. My name is Alan B. Meginnis. I am Manager, Product Licensing, for Framatome Inc. and as such I am authorized to execute this Affidavit.
| |
| : 2. I am familiar with the criteria applied by Framatome to determine whether certain Framatome information is proprietary. I am familiar with the policies established by Framatome to ensure the proper application of these criteria.
| |
| : 3. I am familiar with the Framatome information contained in the report ANP-3758P, Revision 1, "Brunswick Unit 1 Cycle 23 ATRIUM 11 Fuel Nuclear Fuel Design Report," dated September 2019 and referred to herein as "Document." Information contained in this Document has been classified by Framatome as proprietary in accordance with the policies established by Framatome for the control and protection of proprietary and confidential information.
| |
| : 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by Framatome and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
| |
| : 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."
| |
| : 6. The following criteria are customarily applied by Framatome to determine whether information should be classified as proprietary:
| |
| (a) The information reveals details of Framatome's research and development plans and programs or their results.
| |
| (b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
| |
| (c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for Framatome.
| |
| (d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for Framatome in product optimization or marketability.
| |
| (e) The information is vital to a competitive advantage held by Framatome, would be helpful to competitors to Framatome, and would likely cause substantial harm to the competitive position of Framatome.
| |
| The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d) and 6(e) above.
| |
| : 7. In accordance with Framatome's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside Framatome only as required and under suitable agreement providing for nondisclosure and limited use of the information.
| |
| : 8. Framatome policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
| |
| : 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
| |
| | |
| STATE OF WASHINGTON )
| |
| ) ss.
| |
| COUNTY OF BENTON )
| |
| SUBSCRIBED before me this / /,,~day oi'S ~_j,if, 2019 .
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| NOTARY PUBLIC, STATE OF WASHINGTON 1
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| MY COMMISSION EXPIRES: 1/14/2020}}
| |
