ML101160155
| ML101160155 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/31/2010 |
| From: | AREVA, AREVA NP |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC ME0438, TAC ME2451 ANP-2863(NP), Rev 1 | |
| Download: ML101160155 (286) | |
Text
ATTACHMENT 13 Browns Ferry Nuclear Plant (BFN)
Unit I Technical Specifications (TS) Change 473 AREVA Fuel Transition Reload Safety Analysis Report Attached is the non proprietary version of the Reload Safety Analysis Report.
ANP-2863(NP)
Revision 1 Browns Ferry Unit 1 Cycle 9 Reload Safety Analysis for 105% OLTP March 2010 AREVA NP Inc. 'AR EVA
AREVA NP Inc.
ANP-2863(NP)
Revision 1 Browns Ferry Unit I Cycle 9 Reload Safety Analysis for 105% OLTP
AREVA NP Inc.
ANP-2863(NP)
Revision 1 Copyright © 2010 AREVA NP Inc.
All Rights Reserved sip
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page i Nature of Changes Item Page Description and Justification
- 1. 2-2 Revised formatting of last paragraph.
- 2. 4-1, 5-1 Removed footnote and text referring to Reference 31. Reference 5 has been updated resulting in no need for Reference 31 or the footnote.
- 3. Section 6.1 The section is revised to reflect the analysis presented in References 19 and 20.
- 4. Section 9.0 References 5, 19, and 20 are updated. References 31, 40, and 42 are removed. Reference 41 in Revision 0 is now Reference 40.
- 5. Appendix A The figure number format is updated throughout the Appendix.
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ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page ii Contents 1.0 Introduction .................................................................................................................... 1-1 2.0 Disposition of Events ...................................................................................................... 2-1 3.0 Mechanical Design Analysis .......................................................................................... 3-1 4.0 Therm al-Hydraulic Design Analysis ............................................................................... 4-1 4.1 Therm al-Hydraulic Design and Com patibility ..................................................... 4-1 4.2 Safety Lim it MCPR Analysis ............................................................................... 4-1 4.3 Core Hydrodynam ic Stability .............................................................................. 4-2 5.0 Anticipated O perational Occurrences ............................................................................ 5-1 5.1 System Transients .............................................................................................. 5-1 5.1.1 Load Rejection No Bypass (LRNB) ...................................................... 5-3 5.1.2 Turbine Trip No Bypass (TTNB) ........................................................... 5-3 5.1.3 Feedwater Controller Failure (FW CF) .................................................. 5-4 5.1.4 Loss of Feedwater Heating ................................... ......................... 5-5 5.1.5 Control Rod W ithdrawal Error .............................................................. 5-5 5.2 Slow Flow Runup Analysis ................................................................................. 5-6 5.3 Equipm ent O ut-of-Service Scenarios ................................................................. 5-7 5.3.1 TBVOO S .............................................................................................. 5-7 5.3.2 EO C-RPT-O O S .................................................................................... 5-8 5.3.3 FHO OS ................................................................................................. 5-8 5.3.4 PLUOO S .............................................................................................. 5-8 5.3.5 Com bined EO C-RPT-O OS and TBVO OS ............................................ 5-9 5.3.6 Com bined EO C-RPT-O OS and FHOO S .............................................. 5-9 5.3.7 Com bined EO C-RPT-O O S and PLUOO S ............................................ 5-9 5.3.8 Com bined TBVO O S and FHOO S .................... I................................... 5-9 5.3.9 Com bined TBVO O S and PLUOO S ...................................................... 5-9 5.3.10 Com bined FHOO S and PLUOO S ..................................................... 5-10 5.3.11 Combined EOC-RPT-OOS, TBVOOS, and FHOOS .......................... 5-10 5.3.12 Combined EOC-RPT-OOS, TBVOOS, and PLUOOS ........................ 5-10 5.3.13 Combined EOC-RPT-OOS, FHOOS, and PLUOOS .......................... 5-10 5.3.14 Combined TBVOOS, FHOOS, and PLUOOS .................................... 5-10 5.3.15 Combined EOC-RPT-OOS, TBVOOS, FHOOS, and PLUO OS ............................................................................................ 5-11 5.3.16 Single-Loop O peration ....................................................................... 5-11 5.4 Licensing Power Shape .................................................................................... 5-11 6.0 Postulated Accidents ..................................................................................................... 6-1 6.1 Loss-of-Coolant-Accident (LO CA) ...................................................................... 6-1 6.2 Control Rod Drop Accident (CRDA) ................................................................... 6-2 6.3 Fuel and Equipm ent Handling Accident ............................................................. 6-2 6.4 Fuel Loading Error (Infrequent Event) ................................................................ 6-3 6.4.1 Mislocated Fuel Bundle ........................................................................ 6-3 6.4.2 Misoriented Fuel Bundle ....................................................................... 6-3 7.0 Special Analyses ............................................................................................................ 7-1 7.1 ASM E Overpressurization Analysis .................................................................... 7-1 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page iii 7.2 ATW S Event Evaluation ..................................................................................... 7-2 7.2.1 ATWS Overpressurization Analysis ..................................................... 7-2 7.2.2 Long-Term Evaluation .......................................................................... 7-2 7.3 Standby Liquid Control System ........................................................................ 7-4 7.4 Fuel Criticality ............................................. 7-4 8.0 Operating Limits and COLR Input .................................................................................. 8-1 8 .1 MC P R Lim its ...................................................................................................... 8-1 8 .2 LHG R Lim its ....................................................................................................... 8 -1 8.3 MA P LH G R Lim its .............................................................................................. 8-2 9 .0 R efere nces ..................................................................................................................... 9-1 Appendix A Operating Limits and Results Comparisons ................................................. A-1 Tables 1.1 EOD and EOOS Operating Conditions ........................................................................... 1-2 2.1 Disposition of Events Summary for Browns Ferry Unit 1 .............................................. 2-3 2.2 Disposition of Operating Flexibility and EOOS Options on Limiting Events ................. 2-12 2.3 Methodology and Evaluation Models for Cycle Specific Reload Analyses ................... 2-13 4.1 Fuel- and Plant-Related Uncertainties for Safety Limit MCPR Analyses ....................... 4-4 4.2 Results Summary for Safety Limit MCPR Analyses ....................................................... 4-5 4 .3 O P R M S etpoints ............................................................................................................ 4-6 4.4 BSP Endpoints for Browns Ferry Unit 1 Cycle99............................................................ 4-7 5.1 Exposure Basis for Browns Ferry Unit 1 Cycle 9 Transient Analysis ............ 5-13 5.2 Scram Speed Insertion Times ..................................................................................... 5-14 5.3 NEOC Base Case LRNB Transient Results ................................................................. 5-15 5.4 EOCLB Base Case LRNB Transient Results ............................ 5-16 5.5 NEOC Base Case FWCF Transient Results ................................................................ 5-17 5.6 EOCLB Base Case FWCF Transient Results .............................................................. 5-18 5.7 Loss of Feedwater Heating Transient Analysis Results ..................... 5-19 5.8 Control Rod Withdrawal Error ACPR Results ............................................................... 5-20 5.9 RBM Operability Requirements ..................................................................................... 5-21 5.10 Flow-Dependent MCPR Results ................................................................................. 5-22 5.11 Licensing Basis Core Average Axial Power Profile ..................................................... 5-23 7.1 ASME Overpressurization Analysis Results ................................................................... 7-5 7.2 ATWS Overpressurization Analysis Results .............................. 7-6 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page iv 7 .3 ......................... 7-7 8.1 MCPRP Limits for NSS Insertion Times BOC to NEOC .................................................. 8-3 8.2 MCPRP Limits for TSSS Insertion Times BOC to NEOC................................................ 8-7 8.3 MCPRp Limits for NSS Insertion Times BOC to EOCLB ................................................. 8-11 8.4 MCPRP Limits for TSSS Insertion Times BOC to EOCLB ............................................ 8-15 8.5 MCPRp Limits for NSS Insertion Times BOC to FFTR/Coastdown .............................. 8-19 8.6 MCPRP Limits for TSSS Insertion Times BOC to FFTR/Coastdown ............................ 8-22 8.7 Flow-Dependent MCPR Limits ATRIUM-10 and GE14 Fuel ........................................ 8-25 8.8 ATRIUM-10 Steady-State LHG R Lim its ...................................................................... 8-26 8.9 ATRIUM-10 LHGRFACp Multipliers for NSS/TSSS Insertion Times All C ycle 9 E xposures ..:............................. ;...................................................................... 8-27 8.10 GE14 LHGRFACp Multipliers for NSS/TSSS Insertion Times All Cycle 9 E xp o s u re s .................................................................................................................... 8 -2 8 8.11 ATRIUM-10 LHGRFACf Multipliers All Cycle 9 Exposures ................... 8-29 8.12 GE14 LHGRFACf Multipliers All Cycle 9 Exposures ................................................... 8-30 8.13 ATR IUM-10 MA PLH G R Lim its ..................................................................................... 8-31 Figures 1.1 Browns Ferry Power/Flow Map - 105% OLTP .............................................................. 1-3 4.1 Core-wide Radial Power Histogram for Limiting TLO Exposure .................................... 4-8 4.2 Core-wide Radial Power Histogram for Limiting SLO Exposure .................................... 4-9 5.1 EOCLB LRNB at 1OOP/1 05F - TSSS Key Parameters ................................................ 5-24 5.2 EOCLB LRNB at 1OOP/105F - TSSS Sensed Water Level ......................................... 5-25 5.3 EOCLB LRNB at 1OOP/105F - TSSS Vessel Pressures ............................................. 5-26 5.4 EOCLB FWCF at looP/1 05F - TSSS Key Parameters ............................................... 5-27 5.5 EOCLB FWCF at 1OOP/105F - TSSS Sensed Water Level ........................................ 5-28 5.6 EOCLB FWCF at 100P/105F - TSSS Vessel Pressures .................... 5-29 7.1 MSIV Closure Overpressurization Event at 102P/105F - Key Parameters ................... 7-8 7.2 MSIV Closure Overpressurization Event at 102P/105F - Sensed Water Le ve l............................................................................................................................... 7 -9 7.3 MSIV Closure Overpressurization Event at 102P/105F - Vessel P re ss u re s ........................................................................................... ;......................... 7 -10 7.4 MSIV Closure Overpressurization Event at 102P/105F - Safety/Relief V a lve Flow Rates ......................................................................................................... 7-11 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page v 7.5 PRFO ATWS Overpressurization Event at 1OOP/81F - Key Parameters .................... 7-12 7.6 PRFO ATWS Overpressurization Event at 100P/81F - Sensed Water Le v e l............................................................................................................................. 7-1 3 7.7 PRFO ATWS Overpressurization Event at 1 00P/81 F - Vessel Pressures .................. 7-14 7.8 PRFO ATWS Overpressurization Event at 1 OOP/81 F - Safety/Relief V a lve F low Rates ......................................................................................................... 7-15 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page vi Nomenclature 2PT two pump trip ADS automatic depressurization system AOT abnormal operational transient APLHGR average planar linear heat generation rate ARO all control rods out ASME American Society of Mechanical Engineers AST alternate source term ATWS anticipated transient without scram ATWS-PRFO anticipated transient without scram pressure regulator failure open ATWS-RPT anticipated transient without scram recirculation pump trip BF1 Browns Ferry Unit 1 BLEU blended low enriched uranium BOC beginning-of-cycle BPWS banked position withdrawal sequence BSP backup stability protection BWR boiling water reactor BWROG Boiling Water Reactor Owners Group CAD containment atmosphere dilution CFR Code of Federal Regulations COLR core operating limits report CPR critical power ratio CRDA control rod drop accident CRWE control rod withdrawal error DIVOM delta-over-initial CPR versus oscillation magnitude ECCS emergency core cooling system EFPD effective full-power days EFPH effective full-power hours EFPY effective full-power years EOC end-of-cycle EOCLB end-of-cycle licensing basis EOC-RPT-OOS end-of-cycle recirculation pump trip out-of-service EOD extended operating domain EOFP end of full power EQOS equipment out-of-service EPU extended power uprate FFTR final feedwater temperature reduction FHOOS feedwater heaters out-of-service FSAR final safety analysis report FW feedwater FWCF feedwater controller failure GE General Electric GNF Global Nuclear Fuels AREVA NP Inc.
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Browns Ferry Unit I Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page vii Nomenclature (Continued)
HCOM hot channel oscillation magnitude HFR heat flux ratio HPCI high pressure coolant injection ICF increased core flow IHPS inadvertent HPCI pump start IORV inadvertent opening of a relief valve 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 LOFW loss of feedwater flow LPRM local power range monitor LRNB generator load rejection with no bypass 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 MSIV main steam isolation valve MSRV main steam relief valve MSRVOOS main steam relief valve out-of-service NEOC near end-of-cycle NSS nominal scram speed NRC Nuclear Regulatory Commission, U.S.
OLMCPR operating limit minimum critical power ratio OLTP original licensed thermal power OPRM oscillation power range monitor Pbypass power belowwhich direct scram on TSV/TCV closure is bypassed PCT peak cladding temperature PLU power load unbalance PLUOOS power load unbalance out-of-service PRFO pressure regulator failure open RBM (control) rod block monitor RHR residual heat removal RPT recirculation pump trip AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page viii Nomenclature (Continued)
SLC standby liquid control SLCS standby liquid control system SLMCPR safety limit minimum critical power ratio SLO single-loop operation SS steady state TBVOOS turbine bypass valves out-of-service TBV turbine bypass valves TCV turbine control valve TIP traversing incore probe TIPOOS traversing incore probe out-of-service TLO two-loop operation TSSS technical specifications scram speed TSV turbine stop valve TTNB turbine trip with no bypass TVA Tennessee Valley Authority ACPR change in critical power ratio AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 1-1 1.0 Introduction Reload licensing analyses results generated by AREVA NP Inc.* are presented in support of
,cycle operation. The analyses reported in this document were performed using methodologies previously approved for generic application to boiling water reactors. The Nuclear Regulatory Commission, U.S. (NRC) technical limitations associated with the application of the approved methodologies have been satisfied by these analyses.
The core consists of a total of 764 fuel assemblies, including 272 fresh ATRIUM TM-10Q assemblies and 492 irradiated GE14 assemblies. Licensing analyses support the core design presented in Reference 1.
Reload licensing analyses were performed for potentially limiting events and analyses identified in Section 2. Results of analyses are used to establish the Technical Specifications/COLR limits and ensure design and licensing criteria are met. Design and safety analyses are based on both 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 and also support operation with the equipment out-of-service (EOOS) scenarios presented in Table 1.1.
AREVA NP Inc. is an AREVA and Siemens company.
t ATRIUM is a trademark of AREVA NP.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 1-2 Table 1.1 EOD and EOOS Operating Conditions Extended Operating Domain (EOD) Conditions Increased core flow (ICF)
Maximum extended load line limit analysis (MELLLA)
Combined final feedwater temperaturereduction (FFTR) I coastdown Equipment Out-of-Service (EOOS) Conditions*
Turbine bypass valves out-of-service (TBVOOS)
EOC recirculation pump trip out-of-service (EOC-RPT-OOS)
Feedwater heaters out-of-service (FHOOS)
Power load unbalance out-of-service (PLUOOS)
Combined EOC-RPT-OOS and TBVOOS Combined EOC-RPT-OOS and FHOOS Combined EOC-RPT-OOS and PLUOOS Combined TBVOOS and FHOOS Combined TBVOOS and PLUOOS Combined FHOOS and PLUOOS Combined EOC-RPT-OOS, TBVOOS, and FHOOS Combined EOC-RPT-OOS, TBVOOS, and PLUOOS Combined EOC-RPT-OOS, FHOOS, and PLUOOS Combined TBVOOS, FHOOS, and PLUOOS Combined EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS Single-loop operation (SLO)
SLO may be combined with all of the other EOOS conditions. Base case and each EOOS condition is supported in combination with 1 MSRVOOS, up to 2 traversing incore probe (TIP) machines out-of-service (TIPOOS) or the equivalent number of TIP channels (per operating requirements defined in Section 4.2), and/or up to 50% of the LPRMs out-of-service.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 1-3 140 130 120 110 100
- 90
- 80
.* 70
- 60 50 40 30 20 10 0
0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow (% of Rated)
Figure 1.1 Browns Ferry Power/Flow Map - 105% OLTP AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-1 2.0 Disposition of Events The objective is to identify limiting events for analysis, supporting operation with ATRIUM-10 fuel. Events and analyses identified as potentially limiting are either evaluated generically for the introduction of AREVA fuel or on a cycle-specific basis.
The first step 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 must be met, ensuring regulatory compliance and safe operation. The licensing basis, related to fuel and applicable for reload analysis, is contained in the Final Safety Analysis Report (FSAR), the Technical Specifications, Core Operating Limits Reports (COLR), and other
.reload analysis reports.
This report supports 105% OLTP operation, which is the power level currently supported in the FSAR and Technical Specifications. EPU analyses and documents were considered in support of the disposition of events review (References 33, 34, 35, 36, and 39). The conclusions of the review were the same for both 105% OLTP and 120% OLTP operation.
The main steam turbine for Unit 1 has been modified for 120% OLTP operation. The same turbine modifications have not yet occurred for Units 2 and 3 to support EPU. For 105% OLTP operation, the only significant difference for the reload licensing analyses due to the turbine modifications is the position of the turbine control valve (TCV). The turbine modifications result in the TCV being less open for a given steam flow. This in turn results in an increase in severity for pressurization events with closure of the TCV; for example, the load rejection event. The TCV position is explicitly modeled in the reload analyses for limiting events that have TCV closure and is based on the 120% OLTP modifications. The turbine modifications do not change the conclusion of the disposition of events for BF1 105% OLTP operation.
Except for core loading and the turbine modifications previously discussed, all three Browns Ferry Units (1, 2, and 3) are essentially the same because core operational conditions, modeled geometry, safety system performance, and ECCS parameters are identical. A review of geometry between Units 1, 2, and 3 determined the only significant difference was the recirculation piping for Unit 3 (Unit 3 has undergone a recirculation header and riser replacement). Differences in recirculation piping for Unit 3 do not result in any modifications to the recirculation piping model used in the analyses (simplification of the recirculation piping model does not distinguish the differences). The review of differences between units concluded AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-2 none of the analyses, or dispositions in Reference 34, needed to be revised for Unit 1.
Differences in core design between units are addressed on a cycle-specific basis.
AREVA reviewed all fuel-related design criteria, events, and analyses identified in the licensing basis. In many cases, when operating limits are established to ensure acceptable consequences of an abnormal operational transient (AOT) or accident, the fuel-related aspects of the system design criteria are met. All fuel-related events were reviewed and dispositioned into one of the following categories:
- 1. No further analysis required. This classification may result from one of the following:
- a. The consequences of the event are bound by consequences of a different event.
- b. The consequences of the event are benign, i.e., the event causes no significant change in margins to the operating limits.
- c. The event is not affected by the introduction of a new fuel design and/or the current analysis of record remains applicable.
- 2. Address event each reload. The consequences of the event are potentially limiting and need to be addressed each reload.
- 3. Address for initial reload. This classification may result from one of the following:
- a. 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.
- b. 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.
The impact of operation in the EOOS scenarios presented in Table 1.1 was also considered.
A disposition of events summary is presented in Table 2.1. The disposition summary presents a list of the events and analyses, the corresponding FSAR section, the disposition status, and any applicable comments. In each comment, the basis of the disposition is categorized as:
0 FSAR analysis (which may include Reference 34).
0 Generic analysis. A bounding analysis that is independent of plant type.
- Plant specific analysis. The analysis is based on Browns Ferry (independent of unit) and is bounding for cycle-to-cycle variations.
- Cycle specific analysis. The analysis is specific to the Unit and Cycle.
The disposition for the EOOS scenarios are summarized in Table 2.2. ICF and MELLLA operation regions of the power/flow map are included in the disposition results presented in Table 2.1. Methodology and evaluation models used for the cycle specific analyses are provided in Table 2.3. Overpressurization analyses are performed with the NRC approved code COTRANSA2 (References 12 and 40).
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-3 Table 2.1 Disposition of Events Summary for Browns Ferry Unit I FSAR Section Event /Analysis Disposition Status Comments 3.2 Fuel mechanical Address event for Cycle specific analysis (results and design each reload analyses generally do not change from cycle-to-cycle, unless a design feature is modified).
Refer to Reference 2 for the analysis, acceptance criteria, methodology and evaluation model.
Demonstrate design criteria are met.
3.6 Nuclear design Address event each Cycle specific analysis.
reload Refer to Reference 1 for the analysis, acceptance criteria, methodology and evaluation model.
Demonstrate design criteria are met.
3.7 Thermal and Address event each Plant specific and cycle specific analysis.
hydraulic design reload Demonstrate design criteria are met. Fuel hydraulic design and compatibility results are provided in the Thermal-Hydraulic Design report. Refer to Reference 3 for the analysis, acceptance criteria, methodology and evaluation model. Other cycle specific criteria are presented in this report, i.e., thermal operating limits.
3.8 Standby liquid Address event each Cycle specific analysis.
control system reload Analysis performed each reload to verify adequate SLCS shutdown capacity.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-4 Table 2.1 Disposition of Events Summary for Browns Ferry Unit 1 (Continued)
FSAR Section Event /Analysis Disposition Status Comments 4.2 Reactor vessel and No further analyses FSAR analysis and Reference 34.
appurtenances required The vessel fluence irradiation is primarily mechanical design dependent upon the effective full power years (EFPY), power distribution, power level, and fuel management scheme. The neutron spectrum of the ATRIUM-10 fuel is sufficiently similar to the spectrum applied in the licensing basis evaluation of the vessel irradiation limits. The void, power distributions, and the fission spectrum for ATRIUM-10 fuel are not significantly impacted by BLEU. An evaluation of ATRIUM-10 BLEU fuel flux concluded that the GE EPU analyses remained bounding. The introduction of ATRIUM-10 fuel with or without BLEU will have an insignificant effect on the fluence (E > 1.0 MeV) at the reactor vessel wall and internals.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-5 Table 2.1 Disposition of Events Summary for Browns Ferry Unit 1 (Continued)
FSAR Section Event /Analysis Disposition Status, Comments 4.4 Nuclear system Address event each Cycle specific analysis (overpresurization),
pressure relief reload plant specific analysis (LOCA).
sIystem Analysis of limiting ASME and ATWS overpressurization events required each reload.
Evaluations of the ADS capability are addressed as part of the LOCA analyses (References 19 and 20).
5.2 Primary No further analyses FSAR analysis and Reference 34.
containment required Except for the CAD evaluation, the system primary containment characteristics following a postulated LOCA are not fuel related. The CAD system criteria were met for ATRIUM-1 0. The Unit 1 containment characteristics are the same as Units 2 and 3, therefore the assessment of CAD for those units applies to Unit 1.
5.3 Secondary No further analyses FSAR analysis and Reference 34.
Containment required System The secondary containment basis is independent of fuel design.
6.0 Emergency core Address event each Plant specific analysis and cycle specific cooling systems reload analysis.
LOCA is a potentially limiting accident.
Limiting break characteristics are identified for the initial ATRIUM-10 reload. Refer to References 19 and 20 for the analysis, acceptance criteria, methodology and evaluation model.
LOCA heatup analysis for reload fuel is evaluated for follow-on reloads to address changes in neutronic design.
7.5 Neutron Address event each Plant specific and cycle specific analysis.
monitoring system reload Cycle specific OPRM trip setpoint calculations. RBM setpoints evaluated for the CRWE event. Backup stability protection.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-6 Table 2.1 Disposition of Events Summary for Browns Ferry Unit 1 (Continued)
FSAR Section Event /Analysis Disposition Status Comments 7.19 Anticipated Address event each Cycle specific analysis.
transient without reload scram Analyses are performed to demonstrate that the peak vessel pressure for the limiting ATWS event is less than 120% of design pressure. Long term ATWS analyses remain applicable for ATRIUM-10 (Section 7.2.2).
8.10 Station blackout No further analyses FSAR analysis and Reference 34.
required The licensing basis analysis remains applicable. ATRIUM-10 fuel is designed to perform in a manner similar to and analogous with fuel of current and previous designs.
10.2 New fuel storage Address for initial Plant specific analysis.
reload Refer to Reference 24 for the analysis, acceptance criteria, methodology and evaluation model.
Evaluated for new fuel storage racks.
Confirm applicability each reload.
10.3 Spent fuel storage Address for initial Plant specific analysis.
reload Refer to Reference 25 for the analysis, acceptance criteria, methodology, and evaluation model.
Evaluated for spent fuel storage racks.
Confirm applicability each reload.
10.11 Fire protection Address for initial Plant specific analysis.
systems .re!oad Appendix R criteria are met for ATRIUM-10 fuel. This issue is addressed in Reference 37.
14.5.2.1 Generator trip No further analyses FSAR analysis and Reference 34.
(TCV fast closure) required Bound by the generator trip with turbine bypass valve failure.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-7 Table 2.1 Disposition of Events Summary for Browns Ferry Unit 1 (Continued)
FSAR Section Event /Analysis Disposition Status Comments 14.5.2.2 Generator trip Address event each Cycle specific analysis.
(TCV fast closure) reload with turbine This event is a potentially limiting AOT.
bypass valve failure 14.5.2.2.4 LRNB with EOC- Address event each Cycle specific analysis.
RPT-OOS reload This event is a potentially limiting AOT.
14.5.2.3 Loss of condenser No further analyses FSARanalysis.
vacuum required Bound by the turbine trip with turbine bypass valve failure.
14.5.2.4 Turbine trip (TSV No further analyses FSAR analysis.
closure) required Bound by the turbine trip with turbine bypass valve failure.
14.5.2.5 Turbine bypass Address for initial Cycle specific analysis, for initial reload.
valves failure reload following turbine Generally bound by the generator trip with trip (TTNB), high turbine bypass valve failure.
power 14.5.2.6 Turbine bypass Address for initial Cycle specific analysis, for initial reload.
valves failure reload following turbine Generally bound by the generator trip with trip (TTNB), low turbine bypass valve failure. If 14.5.2.5 is power bound by generator trip with turbine bypass valve failure, then 14.5.2.6 is also bound.
14.5.2.7 Main steam No further analyses FSAR analysis and Reference 34.
isolation valve required closure Relative to thermal operating limits, bound by the generator trip with turbine bypass valve failure.
14.5.2.8 Pressure regulator No further analyses FSAR analysis and Reference 34.
failure (downscale) required Eliminated as an AOT by the installation of a digital fault-tolerant main turbine electro-hydraulic control system.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-8 Table 2.1 Disposition of Events Summary for Browns Ferry Unit 1 (Continued)
FSAR Section Event /Analysis Disposition Status Comments 14.5.3.1 Loss of feedwater Address event each Cycle specific analysis.
heater (LFWH) reload Generally bound by the LRNB and FWCF events. Addressed each cycle to demonstrate that it remains bound by the other events.
14.5.3.2 Shutdown cooling No further analyses FSAR analysis.
(RHR) malfunction required
- decreasing Benign event.
temperature 14.5.3.3 Inadvertent HPCI No further analysis FSAR analysis and Reference 34.
pump start required (IHPS) Generally bound by the LRNB and FWCF events. The IHPS event is similar to the LFWH event. The IHPS is slightly more CPR limiting, whereas the LFWH is slightly more thermal-mechanical limiting.
Both IHPS and LFWH events have considerable margin to the limiting LRNB and FWCF events. The LFWH transient is analyzed for each cycle to demonstrate, on a relative basis, that the LFWH and IHPS events remain non-limiting.
14.5.4.1 Continuous rod Address event each Cycle specific analysis.
withdrawal during reload power range This event is a potentially limiting AOT.
operation 14.5.4.2 Continuous rod No further analyses FSAR analysis.
withdrawal during required reactor startup Benign event.
14.5.4.3 Control rod No further analyses FSAR analysis.
removal error required during refueling This event is not credible.
14.5.4.4 Fuel assembly No further analyses FSAR analysis.
insertion error required during refueling This event is not credible.
Mislocated or Address event each Generic analysis.
misoriented fuel reload assembly AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-9 Table 2.1 Disposition of Events Summary for Browns Ferry Unit I (Continued)
FSAR Section Event /Analysis Disposition Status Comments 14.5.5.1 Pressure regulator Address event each FSAR analysis and cycle specific analysis.
failure (PRFO)open reload Relative to AOT thermal operating limits, benign event.
PRFO - maximum steam demand is a potentially limiting ATWS overpressurization event. ATWS-PRFO is considered for FSAR 7.19.
14.5.5.2 Inadvertent No further analysis FSAR analysis.
opening of a required MSRV (IORV) Benign event.
14.5.5.3 Loss of feedwater No further analysis FSAR analysis.
flow (LOFW) required Benign event.
14.5.5.4 Loss of auxiliary No further analyses FSAR analysis.
power required Benign event.
14.5.6.1 Recirculation flow No further analysis FSAR analysis.
control failure - required decreasing flow Non-limiting event.
14.5.6.2 Trip of one No further analyses FSAR analysis.
recirculation pump required Consequences of this event are benign and bound by the turbine trip with no bypass event.
14.5.6.3 Trip of two No further analyses FSAR analysis.
recirculation required pumps Consequences of this event are benign and bound by the turbine trip with no bypass event.
14.5.6.4 Recirculation No further analysis FSAR analysis.
pump seizure required The consequences of this accident are bounded by the effects of a LOCA.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-10 Table 2.1 Disposition of Events Summary for Browns Ferry Unit I (Continued)
FSAR Section Event /Analysis Disposition Status Comments 14.5.7.1 Recirculation flow Address event each Cycle specific analysis.
control failure - reload increasing flow Consequences of the slow flow run-up event determine the flow-dependent MCPR and LHGR operating limits and are evaluated each reload.
14.5.7.2 Startup of idle No further analysis FSAR analysis.
recirculation loop required Benign event.
14.5.8.1 Feedwater Address event each Cycle specific analysis.
controller failure reload (FWCF) - This event is a potentially, limiting AOT.
maximum demand 14.5.8.2 Feedwater Address event each Cycle specific analysis.
controller failure reload (FWCF) - This event is a potentially limiting AOT.
maximum demand with EOC-RPT-OOS 14.5.8.3 Feedwater Address event each Cycle specific analysis.
controller failure reload (FWCF) - This event is a potentially limiting AOT.
maximum demand with TBVOOS 14.5.9 Loss of habitability No further analyses FSAR analysis.
of the control room required This is postulated as a special event to demonstrate the ability to safely shutdown the reactor from outside the control room.
14.6.2 Control rod drop Address event each Cycle specific analysis.
accident (CRDA) reload Consequences of the CRDA are evaluated to confirm that the acceptance criteria are satisfied.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-11 Table 2.1 Disposition of Events Summary for Browns Ferry Unit 1 (Continued)
FSAR Section Event /Analysis Disposition Status Comments 14.6.3 Loss-of-coolant Address event each Plant specific analysis and cycle specific accident (LOCA) reload analysis.
Consequences of the LOCA are evaluated to determine appropriate cycle-specific MAPLHGR limits. Refer to References 19 and 20 for the analysis, acceptance criteria, methodology and evaluation model.
LOCA heatup analysis for reload fuel is evaluated for follow-on reloads to address changes in neutronic design.
14.6.4 Refueling accident Address event each Plant specific analysis.
reload Refer to Reference 27 for the analysis, acceptance criteria, methodology and evaluation model.
Consequences of the refueling accident are evaluated to confirm that the acceptance criteria are satisfied.
14.6.5 Main steam line No further analysis FSAR analysis and Reference 34.
break accident required The consequences of a large steam line break are far from limiting with respect to 10 CFR 50.46 acceptance -criteria.
Radiological dose consequences have been performed utilizing AST in accordance with 10 CFR 50.67. The consequences of the event are not a function of fuel type since no fuel failures are calculated to occur. The dose is a function of the radionuclide inventory in the coolant itself prior to the event.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-12 Table 2.2 Disposition of Operating Flexibility and EOOS Options on Limiting Events Option Affected Limiting Comments Events/Analyses One MSRV ASME Overpressurization This scenario is included as part of the base Out-of-Service case condition for the events/analyses FWCF identified.
LRNB TTNB ATWS Single-loop operation LOCA The impact of SLO on LOCA is addressed (SLO) C in Section 8.
The SLO SLMCPR is addressed each reload.
Final Feedwater FWCF This scenario is included in each reload for Temperature Reduction each of these events/analyses.
(FFTR)/Feedwater Option III Stability Solution Heater Out-of-Service Backup Stability Protection (FHOOS) (BSP)
Turbine bypass valve FWCF The FWCF event with TBVOOS is system out-of-service evaluated each reload.
- (TBVOOS)
EOC-RPT out-of-service FWCF This scenario is included in each reload for (EOC-RPT OOS) LRNB each of these events/analyses.
TTNB Power load unbalance LRNB The LRNB event with PLUOOS is evaluated out-of-service each reload.
(PLUOOS)
Traversing in-core probe SLMCPR TIP OOS is included in the SLMCPR (TIP) out-of-service analysis.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-13 Table 2.3 Methodology and Evaluation Models for Cycle Specific Reload Analyses Analysis FSAR Methodology Evaluation Acceptance Criteria and Section Event /Analysis Reference Model Comments 3.7 Thermal and 4 SAFLIM2 SLMCPR criteria: < 0.1% fuel hydraulic design 12 COTRANSA2 rods experience boiling transition.
13 XCOBRA Transient criteria: Power and 14 XCOBRA-T flow dependent MCPR and 16 RODEX2 LHGR operating limits established to meet the fuel failure criteria.
3.8 Standby liquid 15 CASMO-4 SLCS criteria: Shutdown margin control system /MICROBURN- of at least 0.88% Ak/k.
B2 4.4 Nuclear system 12 COTRANSA2 Analyses for ASME and ATWS pressure relief overpressurization.
system ASME overpressurization criteria: Maximum vessel pressure limit of 1375 psig and maximum dome pressure limit of 1325 psig.
ATWS overpressurization criteria: Maximum vessel pressure limit of 1500 psig.
6.0 Emergency core 38 HUXY LOCA criteria: 10CFR50.46.
cooling systems EXEM BWR-2000 Methodology.
Only heatup (HUXY) is analyzed for the reload specific neutronic design.
7.5 Neutron 7 STAIF Long term stability solution monitoring system 8 RAMONA5-FA Option III criteria: OPRM setpoints do not result in 9 CASMO-4 / exceeding OLMCPR limits.
10 MICROBURN-B2 CRWE criteria:
CW rtra Power oe 11 dependent MCPR and LHGR operating limits established to 15 meet the fuel failure criteria.
30 Backup stability protection criteria: Stability boundaries that do not exceed acceptable global, regional and channel decay ratios as defined by the STAIF methodology.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-14 Table 2.3 Methodology and Evaluation Models for Cycle Specific Reload Analyses (Continued)
Analysis FSAR Methodology Evaluation Acceptance Criteria and Section Event /Analysis Reference Model Comments 7.19 Anticipated 12 COTRANSA2 ATWS overpressurization transient without criteria: Maximum vessel scram pressure limit of 1500 psig.
ATWS peak pressure only.
14.5.2.2 Generator trip 12 COTRANSA2 Transient criteria: Power and (TCV fast closure) 13 XCOBRA flow dependent MCPR and with turbine LHGR operating limits bypass valve 14 XCOBRA-T established to meet the fuel failure 16 RODEX2 failure criteria.
14.5.2.2.4 LRNB with EOC- 12 COTRANSA2 Transient criteria: Power RPT-OOS 13 XCOBRA dependent MCPR and LHGR operating limits established to 14 XCOBRA-T meet the fuel failure criteria.
16 RODEX2 14.5.2.5 Turbine bypass 12 COTRANSA2 Transient criteria: Power valves failure 13 XCOBRA dependent MCPR and LHGR following turbine operating limits established to trip (TTNB), high 14 XCOBRA-T meet the fuel failure criteria.
power 16 RODEX2 14.5.2.6 Turbine bypass 12 COTRANSA2 Transient criteria: Power valves failure 13 XCOBRA dependent MCPR and LHGR following turbine operating limits established to trip (TTNB), low 14 XCOBRA-T meet the fuel failure criteria.
power 16 RODEX2 14.5.3.1 Loss of feedwater 15 CASMO-4 Transient criteria: Power heater (LFWH) 18 /MICROBURN- dependent MCPR and LHGR B2 operating limits established to meet the fuel failure criteria 14.5.4.1 Continuous rod 15 CASMO-4 CRWE criteria: Power withdrawal during /MICROBURN- dependent MCPR and LHGR power range B2 operating limits established to operation meet the fuel failure criteria Mislocated or 15 CASMO-4 Mislocated/misoriented criteria:
misoriented fuel /MICROBURN- Small fraction of 10 CFR 50.67 assembly B2 limits Generic analysis.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 2-15 Table 2.3 Methodology and Evaluation Models for Cycle Specific Reload Analyses (Continued)
Analysis FSAR Methodology Evaluation Acceptance Criteria and Section Event /Analysis Reference Model Comments 14.5.7.1 Recirculation flow 14 CASMO-4 Transient criteria: Flow control failure - 15 /MICROBURN- dependent MCPR and LHGR increasing flow B2 operating limits established to XCOBRA meet the fuel failure criteria.
14.5.8.1 Feedwater 12 COTRANSA2 Transient criteria: Power controller failure 13 XCOBRA dependent MCPR and LHGR (FWCF) - operating limits established to maximum demand 14 XCOBRA-T meet the fuel failure criteria.
16 RODEX2 14.5.8.2 Feedwater 12 COTRANSA2 Transient criteria: Power controller failure 13 XCOBRA dependent MCPR and LHGR (FWCF) - operating limits established to maximum demand 14 XCOBRA-T meet the fuel failure criteria.
with EOC-RPT- 16 RODEX2 OOS 14.5.8.3 Feedwater 12 COTRANSA2 Transient criteria: Power controller failure 13 XCOBRA dependent MCPR and LHGR (FWCF) - operating limits established to maximum demand 14 XCOBRA-T meet the fuel failure criteria.
with TBVOOS 16. RODEX2 14.6.2 Control rod drop 15 CASMO-4 CRDA criteria: Maximum accident (CRDA) /MICROBURN- deposited fuel rod enthalpy is B2 less than 280 cal/g.
14.6.3 Loss-of-coolant 38 HUXY LOCA criteria: 10CFR50.46.
accident (LOCA) EXEM BWR-2000 Methodology.
Only heatup (HUXY) is analyzed for the reload specific neutronic design.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 3-1 3.0 Mechanical Design Analysis Mechanical design exposure limits for ATRIUM-10 fuel are presented in Reference 2. The maximum exposure limits for the ATRIUM-1 0 reload fuel are:
54.0 GWd/MTU average assembly exposure 62.0 GWd/MTU rod average exposure (full-length fuel rods)
Maximum exposure limits for GE14 fuel assemblies remain unchanged from that presented in Reference 26.
The fuel cycle design analyses (Reference 1) verified all fuel assemblies remain within licensed burnup limits.
The ATRIUM-10 LHGR limits are presented in Section 8.0. The GE14 LHGR limits presented in Section 8.0 ensure that the thermal-mechanical design criteria for GE14 fuel are satisfied.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 4-1 4.0 Thermal-Hydraulic Design Analysis 4.1 Thermal-HydraulicDesign and Compatibility Results of thermal-hydraulic characterization and compatibility analyses are presented in Reference 3. Analysis results demonstrate the thermal-hydraulic design and compatibility criteria are satisfied for the transition core consisting of ATRIUM-10 and GE14 fuel.
4.2 Safety Limit MCPR Analysis The safety limit MCPR (SLMCPR) is defined as the minimum value of the critical power ratio ensuring less than 0.1% of the fuel rods are expected to experience boiling transition during normal operation, or an abnormal operational transient (AOT). The SLMCPR for all fuel was determined using the methodology described in Reference 4. The analysis was performed with a power distribution conservatively representing expected reactor operation throughout the cycle.
SLMCPR analysis used the SPCB critical power correlation additive constants and additive constant uncertainty for ATRIUM-1 0 fuel described in Reference 5. The SPCB additive constants and additive constant uncertainty for the coresident GE14 fuel were developed using the indirect approach described in Reference 6.
Determination of the SLMCPR explicitly includes the effects of channel bow relying on the following assumptions: no fuel channels used for more than one fuel bundle lifetime, and assembly average burnup remains less than 55 GWd/MTU for central ATRIUM-10 and GE14 fuel types. The channel bow local peaking uncertainty is a function of the nominal and bowed local peaking factors and the standard deviation of the channel bow.
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. Radial power factor distributions, corresponding to Table 4.2 results, are shown in Figures 4.1 and 4.2.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 4-2 Analysis results support two-loop operation (TLO) SLMCPR of 1.09 and single-loop operation (SLO) SLMCPR of 1.11. Analysis results including the SLMCPR and the percentage of rods expected to experience boiling transition are summarized in Table 4.2.
4.3 Core Hydrodynamic Stability Browns Ferry has implemented BWROG Long Term Stability Solution Option III (Oscillation Power Range Monitor-OPRM). Reload validation has been performed in accordance with Reference 7. The stability based Operating Limit MCPR (OLMCPR) is provided for two conditions as a function of OPRM amplitude setpoint in Table 4.3. The two conditions evaluated are for a postulated oscillation at 45% core flow steady state operation (SS) and following a two recirculation pump trip (2PT) from the limiting full power operation state point. Power- and Flow-dependent limits provide adequate protection against violation of the SLMCPR for postulated reactor instability as long as the operating limit is greater than or equal to the specified value for the selected OPRM setpoint. Setpoints supporting EOOS operating conditions are provided in Table 4.3.
Evaluations by General Electric (GE) have shown that the generic DIVOM curves specified in Reference 7 may not be conservative for current plant operating conditions for plants which have implemented Stability Option I1l. The non-conservatism was addressed by performing calculations for the relative change in CPR as a function of the calculated hot channel oscillation magnitude (HCOM). Analyses were performed with the RAMONA5-FA code in accordance with Reference 30. The code is a coupled neutronic-thermal-hydraulic three-dimensional transient model for the purpose of determining the relationship between the relative change in ACPR and the HCOM on a plant specific basis. The method was developed consistent with the recommendations of the BWROG in Reference 8. Generation of plant-specific DIVOM data is consistent with the BWROG resolution of the non-conservatism as provided in Reference 9. The stability-based OLMCPRs were calculated using the most limiting calculated change in relative ACPR for a given oscillation magnitude.
In cases where the OPRM system is declared inoperable, Backup Stability Protection (BSP) is provided in accordance with Reference 10. BSP curves have been evaluated using STAIF (Reference 11) to determine endpoints meeting decay ratio criteria for the BSP Base Minimal Region I (scram region) and Base Minimal Region II (controlled entry region). Stability AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 4-3 boundaries based on these endpoints can then be determined using the generic shape generating function from Reference 10. Analyses have been performed to support operation for both nominal, and reduced feedwater temperature conditions (both FFTR and FHOOS).
The STAIF acceptance criteria for the BSP endpoints are global decay ratios < 0.85, and regional and channel decay ratios < 0.80. Endpoints for the BSP regions provided in Table 4.4 have global decay ratios _< 0.85, and regional and channel decay ratios < 0.80.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 4-4 Table 4.1 Fuel- and Plant-Related Uncertainties for Safety Limit MCPR Analyses Parameter Uncertainty Fuel-Related Uncertainties I
Plant-Related Uncertainties Feedwater flow rate 1.8%
Feedwater temperature 0.8%
Core pressure 0.7%
Total core flow rate TLO 2.5%
SLO 6.0%
- [
I AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 4-5 Table 4.2 Results Summary for Safety Limit MCPR Analyses Percentage SLMCPR of Rods in Boiling Transition TLO - 1.09 0.086 SLO - 1.11 0.069 AREVA NP Inc.
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Browns Ferry Unit I Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 4-6 Table 4.3 OPRM Setpoints OPRM OLMCPR OLMCPR Setpoint (SS) (2PT) 1.05 1.18 1.15 1.06 1.20 1.17 1.07 1.22 1.19 1.08 1.24 1.21 1.09 1.26 1.23 1.10 1.28 1.25 1.11 1.30 1.26 1.12 1.32 1.29 1.13 1.34 1.31 1.14 1.36 1.33 1.15 1.39 1.35 Rated Power Off-Rated OLMCPR as Acceptance OLMCPR described in Criteria at 45% Flow Section 8.0 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 4-7 Table 4.4 BSP Endpoints for Browns Ferry Unit I Cycle 9 Feedwater Temperature Operation End Point Power Flow Mode Region Designation (% rated) (% rated)
Nominal Scram IA 65.22 41.50 Nominal Scram l1B 43.88 29.00 Nominal Controlled IIA 73.46 50.00 entry Nominal Controlled IIB 30.72 29.00 entry FFTR/ Scram IA 69.63 46.00 FHOOS FFTR/ Scram IB 40.00 29.00 FHOOS FFTR/ Controlled IIA 73.46 50.00 FHOOS entry FFTR/ Controlled IIB 30.72 29.00 FHOOS entry AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 4-8 200 175 150 "J 125 0 100 E 75 z
50 25 0 FT4 _1_
.0 .1 .2 .3 .4 .5 .6 .7 .8 .9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 Radial Power Peaking Figure 4.1 Core-wide Radial Power Histogram for Limiting TLO Exposure AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision I Reload Safety Analysis for 105% OLTP Page 4-9 200 175 150 125 (I
z1 100 I I I I I I I 75 50 25 0 P
.0 .1 .2 .3 .4 .5 .6 .7 .8 .9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 Radial Power Peaking Figure 4.2 Core-wide Radial Power Histogram for Limiting SLO Exposure AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-1 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.
COTRANSA2 (Reference 12), XCOBRA-T (Reference 13), XCOBRA (Reference 14), and CASMO-4/MICROBURN-B2 (Reference 15) are the major codes used in the thermal limits analyses as described in the AREVA THERMEX methodology report (Reference 14) and neutronics methodology report (Reference 15). COTRANSA2 is a system transient simulation code, which includes an axial one-dimensional neutronics model that captures the effects of axial power shifts associated with the system transients. XCOBRA-T is a transient thermal-hydraulics code used in the analysis of thermal margins for the limiting fuel assembly. XCOBRA is used in steady-state analyses. The SPCB critical power correlation (Reference 5) is used to evaluate the thermal margin of the ATRIUM-10 and GEl4 fuel. The application of the SPCB correlation to GE14 fuel follows the indirect process described in Reference 6. Fuel pellet-to-cladding gap conductance values are based on RODEX2 (Reference 16) calculations for the BF1 Cycle 9 core.
5.1 System Transients The reactor plant parameters for the system transient analyses were provided by the utility.
Analyses have been performed to determine power-dependent MCPR limits that protect operation throughout the power/flow domain depicted in Figure 1.1.
At BF1, direct scram on turbine stop valve (TSV) position and turbine control valve (TCV) fast closure are bypassed at power levels less than 30% of rated (Pbypass). Scram will occur when the high pressure or high neutron flux scram setpoint is reached. Reference 17 indicates that MCPR limits only need to be monitored at power levels greater than or equal to 25% of rated, which is the lowest power analyzed for this report.
The limiting exposure for rated power pressurization transients is typically at end of full power (EOFP) when the control rods are fully withdrawn. To provide additional margin to the operating limits earlier in the cycle, analyses were also performed to establish operating limits at a near end-of-cycle (NEOC) core average exposure of 28,285 MWd/MTU. Analyses were performed at cycle exposures prior to NEOC to ensure that the operating limits provide the necessary protection. The end-of-cycle licensing basis (EOCLB) analysis was performed at EOFP + 15 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP . Page 5-2 EFPD (core average exposure of 31,523 MWd/MTU). Analyses were also performed to support extended cycle operation with final feedwater temperature reduction (FFTR) and power coastdown. The licensing basis exposures used to develop the neutronics inputs to the transient analyses are presented in Table 5.1.
All pressurization transients assumed that one of the lowest setpoint main steam relief valves (MSRV) was inoperable. The basis supports operation with 1 MSRV out-of-service.
Reductions in feedwater temperature of less than 10°F from the nominal feedwater temperature and variation of +/-10 psi in dome pressure are considered base case operation, not an EOOS condition. Analyses were performed to determine the limiting conditions in the allowable ranges.
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 65 0 F (55 0 F + 10°F bias) at rated power. Analyses were performed to support combined FFTR/Coastdown operation to a core average exposure of 32,198 MWd/MTU. The analyses were performed with the limiting feedwater and dome pressure conditions in the allowable ranges.
System pressurization transient results are sensitive to scram speed assumptions. 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 and the Technical Specifications scram speed (TSSS) insertion times used in the analyses are presented in Table 5.2. The NSS MCPRp limits can only be applied ifthe scram speed test results meet the NSS insertion times. System transient analyses were performed to establish MCPRP limits for both NSS and TSSS insertion times.
Technical Specifications (Reference 17) allow for operation with up to 13 "slow" and 1 stuck control rod. One additional control rod is assumed to fail to scram. Conservative adjustments to the NSS and TSSS scram speeds were made to the analysis inputs to appropriately account for these effects on scram reactivity. For cases below 30% power, the results are relatively insensitive to scram speed, and only TSSS analyses are performed. At 30% power (Pbypass),
analyses were performed, both with and without bypass of the direct scram function, resulting in an operating limits step change.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-3 5.1.1 Load Rejection No Bypass (LRNB)
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. Fast closure of the turbine control valves also causes a reactor scram and RPT. Turbine bypass system 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.
LRNB analyses assume the power load unbalance (PLU) is inoperable for power levels less than 50% of rated. The LRNB sequence of events is different than the standard event when the PLU is inoperable. 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.
LRNB analyses were performed for a range of power/flow conditions to support generation of the thermal limits. Base case limiting LRNB transient analysis results used to generate the NEOC and EOCLB operating limits, for both TSSS and NSS insertion times, are shown in Tables 5.3 and 5.4. Responses of various reactor and plant parameters during the LRNB event initiated at 100% of rated power and 105% of rated core flow with TSSS insertion times are shown in Figures 5.1-5.3.
/
5.1.2 Turbine Trip No Bypass (TTNB)
A turbine trip event can be initiated as a result of several different signals. The initiating signal causes the TSV to close in order to prevent damage to the turbine. The TSV closure creates a compression wave traveling through the steam lines into the vessel causing a rapid pressurization. The increase in pressure results in a decrease in core voids, which in turn causes a rapid increase in power. Closure of the TSV also causes a reactor scram and an RPT which helps mitigate the pressurization effects. Turbine bypass system 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.
In addition to closing the TSV, a signal is also sent to close the TCV in fast mode. The consequences of a fast closure of the TCV are very similar to those resulting from a TSV closure.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-4 The main difference is the time required to close the valves. While the TCV full stroke closure time is greater than that of the TSV (0.150 sec compared to 0.100 sec), the initial position of the TCV is dependent on the initial steam flow. At rated power and lower, the initial position of the TCV is such that the closure time is less than that of the TSV. However, the TCV closure characteristics are nonlinear such that the resulting core pressurization and ACPR may not always bound those of the slower TSV closure.
Analyses were performed demonstrating that the TTNB event is equivalent to or bound by the LRNB event; therefore, the thermal limits established for the LRNB will also protect against the TTNB event.
5.1.3 Feedwater Controller Failure (FWCF)
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 resulting 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.
Valve closure creates a compression wave traveling back to the core, causing void collapse and subsequent rapid power excursion. The closure of the turbine stop valves also initiates a reactor scram and an RPT. In addition to the turbine stop valve closure, the turbine control valves also close in the fast closure mode. Because of the partially closed initial position of the control valves, they will typically close faster than the stop valves and control the pressurization portion of the event. However, TCV closure characteristics are nonlinear so that the resulting core pressurization and ACPR results may not always bound those of the slower TSV closure at rated power (steam flow increases above rated before fast TCV closure). The 'limiting of TCV, or TSV closure, for the initial operating conditions, was used in the FWCF analyses, based on sensitivity analyses. The turbine bypass valves are assumed operable and provide some pressure relief. The core power excursion is mitigated in part by pressure relief, but the primary mechanisms for termination of the event are reactor scram and revoiding of the core.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-5 FWCF analyses were performed for a range of power/flow conditions to support generation of the thermal limits. Tables 5.5 and 5.6 present the base case limiting FWCF transient analysis results used to generate the NEOC and EOCLB operating limits for both TSSS and NSS insertion times. Figures 5.4 - 5.6 show the responses of various reactor and plant parameters during the FWCF event initiated at 100% of rated power and 105% of rated core flow with TSSS insertion times.
5.1.4 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 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.
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.
The increase in steam flow is accommodated by the pressure control system via the TCVs or the turbine bypass valves, so no pressurization occurs. A cycle-specific analysis was performed in accordance with the Reference 18 methodology to determine the change in MCPR for the event. The LFWH results are presented in Table 5.7.
5.1.5 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 5.8 for the analytical unfiltered RBM high power setpoint values of 107% to 117%. At all intermediate and lower power setpoint values, the MCPRP values for ATRIUM-10 and GE14 fuel bound or are equal to the CRWE MCPR values. Analysis results indicate standard filtered RBM setpoint reductions are supported. Analyses demonstrate that the 1 % strain and centerline melt criteria are met for both AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-6 ATRIUM-10 and GE14 fuel, for the LHGR limits and their associated multipliers presented in Sections 8.2 and 8.3. Recommended operability requirements supporting unblocked CRWE operation are shown in Table 5.9, based on the SLMCPR values presented in Section 4.2.
5.2 Slow Flow Runup Analysis Flow-dependent MCPR and LHGR limits are established to support operation at off-rated core flow conditions. Limits are based on the CPR and heat flux changes experienced by the fuel during slow flow excursions. The slow flow excursion event assumes recirculation flow control system failure such that core flow increases slowly to the maximum flow physically attainable 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. A conservatively steep flow runup path was used in the analysis. Analyses were performed to support operation in all the EOOS scenarios.
MCPRf limits are determined for both ATRIUM-10 and GE14 fuel. 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 so an increase in core power, resulting from the maximum increase in core flow, assures the TLO safety limit MCPR is not violated. Calculations were performed over a range of initial flow rates to determine the corresponding MCPR values causing the limiting assembly to be at the safety limit MCPR for the high flow condition at the end of the flow excursion.
Analysis results are presented in Table 5.10. MCPRf limits providing the required protection are presented in Table 8.7. MCPRf limits are applicable for all exposures.
Flow runup analyses were performed with CASMO-4/MICROBURN-B2 to determine flow-dependent LHGR multipliers (LHGRFACf) for ATRIUM-10 fuel. The analysis assumes recirculation flow increases slowly along the limiting rod line to the maximum flow physically attainable by the equipment. A series of flow excursion analyses were performed at several exposures throughout the cycle, starting from different initial power/flow conditions. Xenon is assumed to remain constant during the event. LHGRFACf multipliers are established to provide protection against fuel centerline melt and overstraining of the cladding during a flow runup.
LHGRFACf multipliers are presented in Table 8.11. A process consistent with the GNF thermal-mechanical methodology was used to determine flow-dependent LHGR multipliers (LHGRFACf)
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-7 for GE14 fuel. GE14 LHGRFACf multipliers protecting against fuel centerline melt, and clad overstrain during operation at off-rated core flow conditions, are presented in Table 8.12.
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.
5.3 Equipment Out-of-Service Scenarios The equipment out-of-service (EOOS) scenarios supported for BF1 Cycle 9 operation are shown in Table 1.1. The EOOS scenarios supported are:
- Turbine bypass valves out-of-service (TBVOOS)
- EOC recirculation pump trip out-of-service (EOC-RPT-OOS)
- Combined EOC-RPT-OOS and TBVOOS
- Combined EOC-RPT-OOS and FHOOS
- Combined EOC-RPT-OOS and PLUOOS
- Single-loop operation (SLO) - recirculation loop out-of-service The base case thermal limits support operation with 1 MSRV out-of-service, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. The analyses presented in this section also include these EOOS conditions protected by the base case limits. No further discussion for these EOOS conditions is presented in this section.
5.3.1 TBVOOS The effect of operation with TBVOOS is a reduction in the system pressure relief capacity, which makes the pressurization events more severe. 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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BrownsFerrUnit1 Cycle9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-8 5.3.2 EOC-RPT-OOS When EOC-RPT is inoperable, no credit is assumed for recirculation pump trip on TSV position or TCV fast closure. The function of the EOC-RPT feature is to reduce the severity of the core power excursion caused by the pressurization transient. The RPT accomplishes this by helping revoid the core, thereby reducing the magnitude of the reactivity insertion resulting from the pressurization transient. Failure of the RPT feature can result in higher operating limits.
Analyses were performed for LRNB and FWCF events assuming EOC-RPT-OOS.
5.3.3 FHOOS The FHOOS scenario assumes a feedwater temperature reduction of 65°F (55°F + 10°F bias) at rated power and steam flow. The effect of reduced feedwater temperature is an increase in core inlet subcooling, changing axial power shape and core void fraction. Additionally, steam flow for a given power level decreases because more power is required to increase coolant enthalpy to saturated conditions. Generally, LRNB and TTNB events are less severe with FHOOS conditions due to the decrease in steam flow relative to nominal conditions. FWCF events with FHOOS conditions are generally worse due to a larger change in inlet subcooling and core power prior to the pressurization phase of the event.
Separate FHOOS limits are not needed for operation beyond the EOCLB exposure since a feedwater temperature reduction is included to attain the additional cycle extension to the FFTR/coastdown exposure, i.e., FFTR is equivalent to FHOOS since both are based on the same feedwater temperature reduction.
5.3.4 PLUOOS The PLU device in normal operation is assumed to not function below 50% power. PLUOOS is assumed to mean the PLU device does not function for any power level, and does not initiate fast TCV closure. The following PLUOOS scenario was assumed for the load reject event.
Initially, the TCVs remain in pressure/speed control mode. There is no direct scram or EOC-RPT on valve motion.
Loss of load results in increasing turbine speed. Depending on initial power, a turbine overspeed condition may be reached to initiate a turbine trip resulting in scram and EOC-RPT.
Without a turbine trip signal, scram occurs on either high flux or high dome pressure to terminate the event.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-9 Analyses were performed for LRNB events assuming PLUOOS.
5.3.5 Combined EOC-RPT-OOS and TBVOOS FWCF analyses with both EOC-RPT-OOS and TBVOOS were performed. Operating limits for this combined EOOS scenario were established using these FWCF results and results previously discussed.
5.3.6 Combined EOC-RPT-OOS and FHOOS FWCF analyses with both EOC-RPT-OOS and FHOOS were performed. Operating limits for this combined EOOS scenario were established using these FWCF results and results previously discussed. Separate EOC-RPT-OOS and FHOOS combined limits are not needed for operation beyond the EOCLB exposure since a FW temperature reduction is included to attain the additional cycle extension to the FFTR/coastdown exposure.
5.3.7 Combined EOC-RPT-OOS and PLUOOS LRNB analyses with both EOC-RPT-OOS and PLUOOS were performed. Operating limits for this combined EOOS scenario were established using these LRNB results and results previously discussed.
5.3.8 Combined TBVOOS and FHOOS FWCF analyses with both TBVOOS and FHOOS were performed. Operating limits for this combined EOOS scenario were established using these FWCF results and results previously discussed. Separate TBVOOS and FHOOS combined limits are not needed for operation beyond the EOCLB exposure since a FW temperature reduction is included to attain the additional cycle extension to the FFTR/coastdown exposure.
5.3.9 Combined TBVOOS and PLUOOS Limits were established to support operation with both TBVOOS and PLUOOS. No additional analyses are required to construct MCPRp operating limits for TBVOOS and PLUOOS since TBVOOS and PLUOOS are independent EOOS conditions (TBVOOS only impacts FWCF events; PLUOOS only impacts LRNB events).
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-10 5.3.10 Combined FHOOS and PLUOOS LRNB analyses with both FHOOS and PLUOOS were performed. Operating limits for this combined EOOS scenario were established using these LRNB results and results previously discussed. Separate FHOOS and PLUOOS combined limits are not needed for operation beyond the EOCLB exposure since a FW temperature reduction is included to attain the additional cycle extension to the FFTR/coastdown exposure.
5.3.11 Combined EOC-RPT-OOS, TBVOOS, and FHOOS FWCF analyses with EOC-RPT-OOS, TBVOOS, and FHOOS were performed. Operating limits for this combined EOOS scenario were established using these FWCF results and results previously discussed. Separate EOC-RPT-OOS, TBVOOS, and FHOOS combined limits are not needed for operation beyond the EOCLB exposure since a FW temperature reduction is included to attain the additional cycle extension to the FFTR/coastdown exposure.
5.3.12 Combined EOC-RPT-OOS, TBVOOS, and PLUOOS Limits were established to support operation with EOC-RPT-OOS, TBVOOS, and PLUOOS. No additional analyses are required to construct MCPRp operating limits for EOC-RPT-OOS, TBVOOS, and PLUOOS since TBVOOS and PLUOOS are independent EOOS conditions (TBVOOS only impacts FWCF events; PLUOOS only impacts LRNB events).
5.3.13 Combined EOC-RPT-OOS, FHOOS, and PLUOOS LRNB analyses with EOC-RPT-OOS, FHOOS, and PLUOOS were performed. Operating limits for this combined EOOS scenario were established using these LRNB results and results previously discussed. Separate EOC-RPT-OOS, FHOOS, and PLUOOS combined limits are not needed for operation beyond the EOCLB exposure since a FW temperature reduction is included to attain the additional cycle extension to the FFTR/coastdown exposure.
5.3.14 Combined TBVOOS, FHOOS, and PLUOOS Limits were established to support operation with TBVOOS, FHOOS, and PLUOOS. No additional analyses are required to construct MCPRp operating limits for TBVOOS, FHOOS, and PLUOOS since TBVOOS and PLUOOS are independent EOOS conditions (TBVOOS only impacts FWCF events; PLUOOS only impacts LRNB events). Separate TBVOOS, FHOOS, and PLUOOS combined limits are not needed for operation beyond the EOCLB exposure since a AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-11 FW temperature reduction is included to attain the additional cycle extension to the FFTR/coastdown exposure.
5.3.15 Combined EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS Limits were established to support operation with EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS. No additional analyses are required to construct MCPRp operating limits for EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS since TBVOOS and PLUOOS are independent EOOS conditions (TBVOOS only impacts FWCF events; PLUOOS only impacts LRNB events). Separate EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS combined limits are not needed for operation beyond the EOCLB exposure since a FW temperature reduction is included to attain the additional cycle extension to the FFTR/coastdown exposure.
5.3.16 Single-Loop Operation In SLO, the two-loop operation ACPRs 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.
5.4 Licensing Power Shape The licensing axial power profile used by AREVA 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 31,523 MWd/MTU is given in Table 5.11.
Cycle 9 operation is considered to be in compliance when:
The normalized power generated in the bottom 7 nodes from the projected EOFP solution at the state conditions provided in Table 5.11 is greater than the normalized power generated in the bottom 7 nodes in the licensing basis axial power profile.
The projected EOFP condition occurs at a core average exposure less than or equal to EOCLB.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-12 If the criteria cannot be fully met (i.e., not all 7 nodes are at a higher power than the licensing profile), the licensing basis may nevertheless remain valid but further assessment will be required.
The licensing basis power profile in Table 5.11 was calculated using the MICROBURN-B2 code.
Compliance analyses must also be performed using MICROBURN-B2 or POWERPLEXO-II*.
Note that the power profile comparison should be done without incorporating instrument updates to the axial profile because the updated power is not used in the core monitoring system to accumulate assembly burnups.
- POWERPLEX is a trademark of AREVA NP registered in the United States and various other countries.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-13 Table 5.1 Exposure Basis for Browns Ferry Unit I Cycle 9 Transient Analysis Core Average Exposure (MWd/MTU) Comments 14,285 Beginning of cycle 28,285 Break point for exposure-dependent MCPRp limits (NEOC) 31,523 Design basis rod patterns to EOFP + 15 EFPD (EOCLB) 32,198 Maximum licensing core exposure - including FFTR
/Coastdown 23,458 (16,178)* Cycle 8 EOC (nominal value) 22,925 (15,645)* Cycle 8 EOC (short window) 23,813 (16,533)* Cycle 8 EOC (long window)
- Corresponding Cycle 8 cycle exposure.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-14 Table 5.2 Scram Speed Insertion Times TSSS NSS Control Rod Analytical Analytical Position Time Time (notch) (sec) (sec) 48 (full-out) 0.00 0.00 48 0.20 0.20 46 0.46 0.421 36 1.09 0.991 26 1.86 1.62 6 3.50 3.04 0 (full-in) 4.0 3.5 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-15 Table 5.3 NEOC Base Case LRNB Transient Results Power ATRIUM-10 ATRIUM-10 GE14
(% rated) ACPR HFR ACPR TSSS Insertion Times 100 0.35 1.25 0.34 90 0.36 1.26 0.34 75 0.35 1.24 0.33 50 0.76 1.68 0.75 40 0.83 1.77 0.82 30 0.95 1.87 0.94 25 at > 50%F below Pbypass 1.02 1.94 1.01 25 at < 50%F below Pbypass 0.89 1.71 0.86 NSS Insertion Times 100 0.33 1.23 0.31 90 0.34 1.24 0.32 75 0.33 1.23 0.31 50 0.75 1.68 0.74 40 0.83 1.76 0.82 AREVA NP Inc.
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Browns Ferry Unit I Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-16 Table 5.4 EOCLB Base Case LRNB Transient Results Power ATRIUM-10 ATRIUM-10 GE14
(% rated) ACPR HFR ACPR TSSS Insertion Times 100 0.36 1.30 0.35 90 0.37 1.31 0.36 75 0.37 1.30 0.36 50 0.78 1.70 0.76 40 0.84 1.79 0.83 30 0.96 1.91 0.95 25 at > 50%F below Pbypass 1.02 1.97 1.01 25 at < 50%F below Pbypass 0.89 1.73 0.86 NSS Insertion Times 100 0.34 1.28 0.33 90 0.35 1.29 0.34 75 0.35 1.29 0.34 50 0.77 1.69 0.76 40 0.83 1.79 0.82 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-17 Table 5.5 NEOC Base Case FWCF Transient Results Power ATRIUM-10 ATRIUM-10 GE14
(% rated) ACPR HFR ACPR TSSS Insertion Times 100 0.44 1.37 0.43 90 0.48 1.42 0.48 75 0.54 1.47 0.55 65 0.59 1.52 0.62 60 0.62 1.55 0.65 50 0.71 1.64 0.72 40 0.85 1.78 0.85 30 1.07 1.97 1.07 30 at > 50%F below Pbypass 1.47 2.53 1.56 30 at < 50%F below Pbypass 1.44 2.36 1.56 25 at > 50%F below Pbypass 1.68 2.71 1.77 25 at < 50%F below Pbypass 1.63 2.46 1.74 NSS Insertion Times 100 0.40 1.35 0.40 90 0.45 1.40 0.45 75 0.51 1.45 0.52 65 0.57 1.51 0.60 60 0.60 1.54 0.63 50 0.69 1.63 0.71 40 0.83 1.78 0.83 30 1.06 1.97 1.06 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-18 Table 5.6 EOCLB Base Case FWCF Transient Results ATRIUM-I 0 Power ATRIUM-10 ATRIUM-10 GE14
(% rated) ACPR HFR ACPR TSSS Insertion Times 100 0.44 1.37 0.43 90 0.48 1.46 0.48 75 0.54 1.47 0.55 65 0.59 1.52 0.62 60 0.62 1.55 0.65 50 0.71 1.64 0.72 40 0.85 1.78 0.85 30 1.07 1.97 1.07 30 at > 50%F below Pbypass 1.47 2.53 1.56 30 at < 50%F below Pbypass 1.44 2.50 1.56 25 at > 50%F below Pbypass 1.68 2.71 1.77 25 at < 50%F below Pbypass 1.63 2.46 1.74 NSS Insertion Times 100 0.40 1.35 0.40 90 0.45 1.42 0.45 75 0.51 1.45 0.52 65 0.57 1.51 0.60 60 0.60 1.54 0.63 50 0.69 1.63 0.71 40 0.83 1.78 0.83 30 1.06 1.97 1.06 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-19 Table 5.7 Loss of Feedwater Heating Transient Analysis Results Power ATRIUM-10/GE14
(% rated) ACPR 100 0.10 90 0.10 80 0.11 70 0.12 60 0.13 50 0.15 40 0.18 30 0.22 25 0.26 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-20 Table 5.8 Control Rod Withdrawal Error ACPR Results Analytical RBM Setpoint (without filter) ACPR* CRWE
(%) MCPRt 107 0.28 1.37 111 0.30 1.39 114 0.32 1.41 117 0.35 1.44
- Results are for the most limiting of the ATRIUM-10 or GE14 fuel in the core.
t For rated power and a 1.09 SLMCPR.
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Browns Ferry Unit I Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-21 Table 5.9 RBM Operability Requirements Applicable Thermal Power ATRIUM-10/GE14
_27% and<90% 1.90 SLO
Ž90% 1.47 TLO AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-22 Table 5.10 Flow-Dependent MCPR Results Core ATRIUM-10 GE14 Flow Limiting Limiting
(% rated) MCPR MCPR 30 1.58 1.57 40 1.48 1.45 50 1.43 1.40 60 1.39 1.35 70 1.32 1.32 80 1.27 1.26 90 1.23 1.22 100 1.19 1.17 107 1.09 1.09 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-23 Table 5.11 Licensing Basis Core Average Axial Power Profile State Conditions for Power Shape Evaluation Power, MWt 3458.0 Core pressure, psia 1050.1 Inlet subcooling, Btu/Ibm 24.2 Flow, MIb/hr 107.6 Control state ARO Co.re average exposure 31,523 (EOCLB), MWd/MTU Licensing Axial Power Profile (Normalized)
Node Power Top 25 0.189 24 0.590 23 0.770 22 0.874 21 0.935 20 0.979 19 1.023 18 1.076 17 1.138 16 1.206 15 1.264 14 1.392 13 1.416 12 1.407 11 1.370 10 1.315 9 1.247 8 1.165 7 1.077 6 0.999 5 0.943 4 0.909 3 0.851 2 0.671 Bottom 1 0.194 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-24
-o tD a
0 C
C-)
G) 0~
Figure 5.1 EOCLB LRNB at 1OOP/105F - TSSS Key Parameters AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit I Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-25 0
"4)
N C
a)
E
_)
O 0
U) 4/)
t-(/)
.0 1.0 2.0 3.0 4.0 5.0 Time (seconds)
Figure 5.2 EOCLB LRNB at lOOP/IO5F- TSSS Sensed Water Level AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-26 W
(U 2.0 3.0 Time (seconds)
Figure 5.3 EOCLB LRNB at 1OOP/105F - TSSS Vessel Pressures AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-27 1:,
~1) 0 C
U
'3) 0~
Figure 5.4 EOCLB FWCF at 10OP/105F - TSSS Key Parameters AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-28 0
N E
0 4-,
0 15.0 Time (seconds)
Figure 5.5 EOCLB FWCF at 100P/105F - TSSS Sensed Water Level AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 5-29 U) 0~
U)
V U)
U)
V 0~
15.0 Time (seconds)
Figure 5.6 EOCLB FWCF at 10OPI105F - TSSS Vessel Pressures AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 6-1 6.0 Postulated Accidents 6.1 Loss-of-Coolant-Accident (LOCA)
As discussed in Section 2, the LOCA models, evaluation, and results are the same for all three units for a full core of ATRIUM-10 fuel. The limiting ATRIUM-10 LOCA results are for EPU operation and bound 105% OLTP operation. The basis for applicability of PCT results from full cores of ATRIUM-10 fuel (based on AREVA methods) and GE14 fuel (based on GNF methods) for a mixed (transition) core is provided in Reference 39 Appendix A. Thermal-hydraulic characteristics of the GE14 and ATRIUM-10 fuel designs are similar as presented in Reference
- 3. Therefore, the core response during a LOCA will not be significantly different for a full core of GE14 fuel or a mixed core of GE14 and ATRIUM-10 fuel. In addition, since about 95% of the reactor system volume is outside the core region, slight changes in core volume and fluid energy due to fuel design differences will produce an insignificant change in total system volume and energy. Therefore, the current GE14 LOCA analysis and resulting licensing PCT and MAPLHGR limits remain applicable.
The results of the ATRIUM-10 LOCA analysis are presented in References 19 and 20. The MAPLHGR limits presented in Reference 20 remain valid for ATRIUM-10 fuel.
Limiting Break: 0.25 ft2 split Recirculation Pump Discharge Line Battery (DC) power, Board B Based on the PCT results in Reference 20, the licensing PCT is 1990'F. The MCPR value used in the LOCA analyses is less than the rated power MCPR limits.
The peak local metal-water reaction for the limiting PCT lattice design is 1.99%. The maximum core wide metal-water reaction (for hydrogen generation) for a full ATRIUM-10 core is <1.0%.
The cycle specific ATRIUM-10 reload fuel PCT was calculated to be 1988 0 F; therefore, in terms of PCT, the limiting neutronic design used in Reference 20 remains bounding. The peak local metal-water reaction and total core wide metal-water reaction were calculated to be 2.00% and
<1.0%, respectively. When compared to the acceptance criteria of less than 17% local cladding oxidation thickness, the local metal-water reaction result remains acceptable.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 6-2 Analyses and results support the EOD and EOOS conditions listed in Table 1.1. Note:
TBVOOS, EOC-RPT-OOS, PLUOOS, and TIPOOS/LPRM out-of-service have no direct influence on the LOCA events.
The GE14 LOCA analysis results are presented in References 21 and 26. No system modifications have been made at BF1 that would invalidate the reactor system response assumed in the GE14 LOCA analysis of record.
6.2 ControlRod Drop Accident (CRDA)
Plant startup utilizes a bank position withdrawal sequence (BPWS) including rod worth minimization strategies. CRDA evaluation was performed for both A and B sequence startups consistent with the withdrawal sequences specified by TVA. Approved AREVA generic CRDA methodology is described in Reference 22. Subsequent calculations have shown the methodology is applicable to fuel modeled with the CASMO4/MICROBURN-B2 code system.
Analysis results demonstrate the maximum deposited fuel rod enthalpy is less than 280 cal/g; the estimated number of fuel rods that exceed the fuel damage threshold of 170 cal/g is less than the number of failed rods assumed in FSAR (850 rods).
Maximum dropped control rod worth, mk 10.98 0 -10.58 x 10-6 Core average Doppler coefficient, Ak/k/ F Effective delayed neutron fraction 0.0052 Four-bundle local peaking factor 1.391 Maximum deposited fuel rod enthalpy, cal/g 189.5 Maximum number of rods exceeding 170 cal/g 276 6.3 Fuel and Equipment HandlingAccident The fuel handling accident radiological analysis implementing the alternate source term (AST) as approved in Reference 27 was performed with consideration of ATRIUM-10 core source terms. Fuel assembly and reactor core isotopic inventories used as input to design basis radiological accident analyses are applicable to all three units (Reference 27).The number of failed fuel rods for the ATRIUM-1 0 fuel as previously provided to TVA in Reference 28 for use in the AST analysis is unchanged. No other aspect of utilizing the ATRIUM-10 fuel affects the current analysis; therefore, the AST analysis remains bounding for Cycle 9.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 6-3 6.4 Fuel Loading Error(Infrequent Event)
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 23, the fuel loading error is characterized as an infrequent event. The acceptance criteria is that the offsite dose consequences due to the event shall not exceed a small fraction of the 10 CFR 50.67 limits.
6.4.1 Mislocated Fuel Bundle AREVA has performed a bounding fuel mislocation error analysis and has demonstrated continued applicability of the bounding results. The analysis considered the impact of a mislocated assembly against potential fuel rod failure mechanisms due to increased LHGR and reduced CPR. Based on the analyses, 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 approaches the fuel centerline melt or 1 % strain limits, and less than 0.1 % of the fuel rods are expected to experience boiling transition.
6.4.2 Misoriented Fuel Bundle AREVA has performed a bounding fuel assembly misorientation analysis. The analysis was performed assuming that the limiting assembly was loaded in the worst orientation (rotated 1800), while simultaneously producing sufficient power to be on the MCPR operating limit as if it were oriented correctly. The analysis demonstrates the small fraction of 10 CFR 50.67 offsite dose criteria is conservatively satisfied. A dose consequence evaluation is not necessary since no rod approaches 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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Browns Ferry Unit I Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 7-1 7.0 Special Analyses 7.1 ASME OverpressurizationAnalysis 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 have sufficient capacity and performance to prevent the reactor vessel pressure from reaching the safety limit of 110% of the design pressure.
MSIV closure, TSV closure, and TCV closure (without bypass) analyses were performed with the AREVA plant simulator code COTRANSA2 (Reference 12) for 102% power and both 81%
and 105% flow at the highest cycle exposure. 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. The following assumptions were made in the analysis.
The most critical active component (direct scram on valve position) was assumed to fail.
However, scram on high neutron flux and high dome pressure is available.
To support operation with 1 MSRVOOS, the plant configuration analyzed assumed that one of the lowest setpoint MSRVs was inoperable.
0 TSSS insertion times were used.
- The initial dome pressure was set at the maximum allowed by the Technical Specifications plus an additional 5 psi bias, 1070 psia (1055 psig).
- A fast MSIV closure time of 3.0 seconds was used.
- The analytical limit ATWS-RPT setpoint and function were assumed.
Results of the MSIV closure, TCV closure, and TSV closure overpressurization analyses are presented in Table 7.1. Various reactor plant parameters during the limiting MSIV closure event are presented in Figures 7.1-7.4. The maximum pressure of 1328 psig occurs in the lower plenum. The maximum dome pressure for the same event is 1291 psig. Results demonstrate the maximum vessel pressure limit of 1375 psig and dome pressure limit of 1325 psig are not exceeded for any analyses.
Pressure results include a 7-psi increase to bound a bias in the void-quality correlations. The void-quality bias is further discussed in Reference 32.
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Browns Ferry Unit 1 Cycle 9 Revision I Reload Safety Analysis for 105% OLTP Page 7-2 7.2 A TWS Event Evaluation 7.2.1 ATWS Overpressurization Analysis This section describes 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). Overpressurization analyses were performed at 100% power at both 81% and 105% flow over the cycle exposure range for both the MSIV closure event and the pressure regulator failure open (PRFO) events. The PRFO event assumes a step decrease in pressure demand such that the pressure control system opens the turbine control and turbine bypass valves. Steam flow demand is assumed to increase to 125% demand (equivalent to 152.46% of rated steam flow) allowing a maximum TCV flow of 122.0% and a maximum bypass system flow-of 25.2%. The system pressure decreases until the low pressure setpoint is reached resulting in the closure of the MSIVs. The subsequent pressurization wave collapses core voids, thereby increasing core power.
The following assumptions were made in the analyses.
- The analytical limit ATWS-RPT setpoint and function were assumed.
- To support operation with 1 MSRVOOS, the plant configuration analyzed assumed that one of the lowest setpoint MSRVs was inoperable.
- All scram functions were disabled.
- The initial dome pressure was set to the nominal pressure of 1050 psia.
- A nominal MSIV closure time of 4.0 seconds was used for both events.
Analyses results are presented in Table 7.2. The response of various reactor plant parameters during the limiting PRFO event are shown in Figures 7.5-7.8. The maximum lower plenum pressure is 1403 psig and the maximum dome pressure is 1384 psig. The results demonstrate that the ATWS maximum vessel pressure limit of 1500 psig is not exceeded.
Pressure results include a 10-psi increase to bound a bias in the void-quality correlations. The void-quality bias is further discussed in Reference 32.
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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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 7-3 I
r I
The suppression pool temperature and containment pressure limits and the corresponding licensing values of record (Reference 36) are presented in the following table. The results are for EPU operation and bound 105% OLTP operation.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 7-4 ATWS Criteria Limit Licensing Value Suppression pool temperature (OF) 281 187.3 Drywell pressure (psig) 56 48.5 Wetwell pressure (psig) 56 30.5 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.
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 Browns Ferry Unit 1 SLC system is required to be able to inject 720 ppm natural boron equivalent at 70°F into the reactor coolant. AREVA has performed an analysis demonstrating the SLC system meets the required shutdown capability for the cycle. The analysis was performed at a coolant temperature of 366 0 F, with a boron concentration equivalent to 720 ppm at 68 0 F*. The temperature of 366 0 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 2.83%
Ak/k based on the Cycle 8 EOC short window, which is the most limiting exposure bound by the short and long Cycle 8 exposure window.
7.4 Fuel Criticality The new fuel storage vault criticality analysis for ATRIUM-10 fuel is presented in Reference 24.
The spent fuel pool criticality analysis for ATRIUM-10 fuel is presented in Reference 25. The ATRIUM-10 fuel assemblies identified for the cycle meet both the new and spent fuel storage requirements.
- VA Browns Ferry SLC licensing basis documents indicate a minimum of 720 ppm boron at a temperature of 70'F. The AREVA cold analysis basis of 68'F represents a negligible difference and the results are adequate to protect the 70°F licensing basis for the plant.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for. 105% OLTP Page 7-5 Table 7.1 ASME Overpressurization Analysis Results*
Maximum Peak Peak Vessel Maximum' Neutron Heat Pressure Dome Flux Flux Lower-Plenum Pressure Event (% rated) (% rated) (psig) (psig)
MSIV closure 295 125 1328 1291 (102P/1 05F)
MSIV closure 317 126 1315 1284 (102P/81 F)
TSV closure without bypass 553 133 1327 1289 (1 02P/1 05F)
TSV closure without bypass 393 130 1310 1280 (102P/81 F)
TCV closure without bypass 555 133 1327 1289 (1 02P/1 05F)
TCV closure without bypass 391 130 1311 1280 (102P/81 F)
Pressure 1375 1325 Limit 1
- Pressure results include a 7-psi increase to bound a bias in the void-quality correlations (Reference 32).
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Browns Ferry Unit 1 Cycle 9 Revision I Reload Safety Analysis for 105% OLTP Page 7-6 Table 7.2 ATWS Overpressurization Analysis Results*
Maximum Peak Peak Vessel Maximum Neutron Heat Pressure Dome Flux Flux Lower-Plenum Pressure Event (%rated) (% rated) (psig) (psig)
MSIV closure 279 140 1382 1360 (1OOP/1 05F)
MSIV closure 296 136 1394 1374 (1OOP/81 F)
PRFO 277 152 1390 1368 (1OOP/1 05F)
PRFO 297 145 1403 1384 (10OP/81F)
Pressure 1500 1500 Limit
- Pressure results include a 10-psi increase to bound a bias in the void-quality correlations (Reference 32).
AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 7-7 Table 7.3 [
I I
I I
t I
AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 7-8 V
'2) 0 0
C
~2)
C-)
0) 0~
6.0 Time (seconds)
Figure 7.1 MSIV Closure Overpressurization Event at 102P/105F - Key Parameters AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 7-9 0
CD E
0) 6.0 Time (seconds)
Figure 7.2 MSIV Closure Overpressurization Event at 102P/105F - Sensed Water Level AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit I Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 7-10 0
(0 0~
(0 CO CO
'I)
L 0~
6.0 Time (seconds)
Figure 7.3 MSIV Closure Overpressurization Event at 102P/105F - Vessel Pressures AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 7-11 C-)
CV)
'N E
-0 0
6) 6)
-I; C
6) ci 6.0 Time (seconds)
Figure 7.4 MSIV Closure Overpressurization Event at 102P/1 05F - Safety/Relief Valve Flow Rates AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 7-12
-o 0
0,.
U) lO.O 03_
Figure 7.5 PRFO ATWS Overpressurization Event at 1OOP/81 F - Key Parameters AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 7-13 0
N E
E L
o 4,
03 Q.
20.0 31 Time (seconds)
Figure 7.6 PRFO ATWS Overpressurization Event at 100P/81 F - Sensed Water Level AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 7-14 1600.0 1400.0
.2 1200.0 CL 1000.0 800.0 600.0 20.0 30.0 Time (seconds)
Figure 7.7 PRFO ATWS Overpressurization Event at 100 P/81 F - Vessel Pressures AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 7-15 IuO.0 .
Low Setpt (3)
Med_Se pt_.(__*)_._
1250.0 -
a)
E S1000.0-a I I
> 75o.0-5000 250.0-n
.0 10.0 20.0 30.0 40.o 50.0 Time (seconds)
Figure 7.8 PRFO ATWS Overpressurization Event at 100P1/81 F - Safety/Relief Valve Flow Rates AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision I Reload Safety Analysis for 105% OLTP Page 8-1 8.0 Operating Limits and COLR Input 8.1 MCPR Limits Determination of MCPR limits are based on analyses of the limiting abnormal operational transients (AOTs). 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 AOT initiated from rated or off-rated conditions and are based on the Technical Specifications two-loop operation SLMCPR of 1.09 and a single-loop operation SLMCPR of 1.11. Exposure-dependent MCPR limits were established to support operation from BOC to near end-of-cycle (NEOC), NEOC to end-of-cycle licensing basis (EOCLB) and combined FFTRlCoastdown. MCPR limits are established to support base case operation and the EOOS scenarios presented in Table 1.1.
Two-loop operation MCPRP limits for ATRIUM-10 and GE14 fuel are presented in Tables 8.1-8.6 for base case operation and the EOOS conditions. Limits are presented for nominal scram speed (NSS) and Technical Specification scram speed (TSSS) insertion times for the exposure ranges considered. Tables 8.1 and 8.2 present the MCPRP limits for the BOC to NEOC exposure range. Tables 8.3 and 8.4 present the MCPRp limits applicable for the BOC to EOCLB exposure range. Tables 8.5 and 8.6 present the MCPRp limits for FFTRFCoastdown operation.
MCPRP limits for single-loop operation are 0.02 higher for all cases. Comparisons of the limiting AOT analysis results and the MCPRP limits for ATRIUM-10 and GE14 fuel are presented in Appendix A.
MCPRf limits protect against fuel failures during a postulated slow flow excursion. ATRIUM-10 and GE14 fuel limits are presented in Table 8.7 and are applicable for all cycle exposures and EOOS conditions identified in Table 1.1.
8.2 LHGR Limits The LHGR limits for ATRIUM-10 are presented in Table 8.8. The LHGR limits for GEI4 fuel are presented in Reference 29. 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 AOT.
LHGRFACp multipliers for ATRIUM-1 0 fuel are determined using the heat flux ratio results from the transient analyses. The LHGRFACP and LHGRFACf multipliers were developed in a manner consistent with the GNF thermal-mechanical methodology for GE14 fuel.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-2 LHGRFACP multipliers were established to support operation at all cycle exposures for both NSS and TSSS insertion times and for the EOOS conditions identified in Table 1.1 with and without TBVOOS. LHGRFACp limits are presented in Tables 8.9 and 8.10 for ATRIUM-1 0 and GE14 fuel, respectively. Comparisons of the limiting results and the LHGRFACP limits are presented in Appendix A.
LHGRFACf multipliers are established to provide protection against fuel centerline melt and overstraining of the cladding during a postulated slow flow excursion. LHGRFACf limits are presented in Table 8.11 and 8.12 for ATRIUM-10 and GE14 fuel, respectively. LHGRFACf multipliers are applicable for all cycle exposures and EOOS conditions identified in Table 1.1.
The SLO LHGR multiplier for GE14 fuel is presented in References 21 and 26.
8.3 MAPLHGR Limits ATRIUM-10 MAPLHGR limits are discussed in Reference 20. The TLO operation limits are presented in Table 8.13. For operation in SLO, a multiplier of 0.85 must be applied to the TLO MAPLHGR limits. Power and flow dependent MAPFAC setdowns are not required; therefore, MAPFAC=1.0.
The GE14 APLHGR limits are discussed in References 21 and 26. The TLO and SLO operation limits are presented in References 21 and 26.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-3 Table 8.1 MCPRP Limits for NSS Insertion Times BOC to NEOC*
MCPRp Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.49 1.49 90.0 1.55 1.55 50.0 1.78 1.80 50.0 1.84 1.83 Base case 40.0 1.92 1.92 operation 30.0 2.15 2.15 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 100.0 1.52 1.52 90.0 1.58 1.58 5 0 .0 ......
50.0 1.84 1.83 40.0 1.96 1.96 TBVOOS 30.0 2.19 2.19 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at* 50%F 3.04 3.17 100.0 1.49 1.49 90.0 1.55 1.55 50.0 1.78 1.80 50.0 1.84 1.83 40.0 1.92 1.92 30.0 2.15 2.15 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 100.0 1.52 1.51 90.0 1.59 1.58 5 0 .0 ......
50.0 1.84 1.87 40.0 2.00 2.01 30.0 2.24 2.24 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96
- Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-4 Table 8.1 MCPRp Limits for NSS Insertion Times BOC to NEOC (Continued)
MCPRP Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.49 1.49 90.0 1.55 1.55 5 0 .0 ......
50.0 1.89 1.87 40.0 1.92 1.92 30.0 2.15 2.15 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 100.0 1.52 1.52 90.0 1.58 1.58 5 0 .0 .... ..
50.0 1.84 1.83 EOC-RPT-OOS 40.0 1.96 1.96 and TBVOOS 30.0 2.19 2.19 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at:<50%F 3.04 3.17 100.0 1.52 1.51 90.0 1.59 1.58 50.0 ---
50.0 1.84 1.87 EOC-RPT-OOS 40.0 2.00 2.01 and FHOOS 30.0 2.24 2.24 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.49 1.49 90.0 1.55 1.55 5 0 .0 ......
50.0 1.89 1.87 EOC-RPT-OOS 40.0 1.92 1.92 and PLUOOS 30.0 2.15 2.15 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-5 Table 8.1 MCPRp Limits for NSS Insertion Times BOC to NEOC (Continued)
MCPRP Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.55 1.54 90.0 1.61 1.61 50 .0 . ... ..
50.0 1.87 1.90 TBVOOS 40.0 2.03 2.04 and FHOOS 30.0 2.27 2.27 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.52 1.52 90.0 1.58 1.58 50.0 --- --
50.0 1.89 1.!87 TBVOOS 40.0 1.96 1.96 and PLUOOS 30.0 2.19 2.19 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at < 50%F 3.04 3.17 100.0 1.52 1.51 90.0 1.59 1.58 50 .0 ......
50.0 1.89 1.87 FHOOS 40.0 2.00 2.01 and PLUOOS 30.0 2.24 2.24 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.55 1.54 90.0 1.61 1.61 50 .0 ......
EOC-RPT-OOS, 50.0 1.87 1.90 EO OO, 40.0 2.03 2.04 TBVOOS, 30.0 2.27 2.27 and FHOOS 3. .722 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-6 Table 8.1 MCPRp Limits for NSS Insertion Times BOC to NEOC (Continued)
MCPRP Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.52 1.52 90.0 1.58 1.58 5 0 .0 ......
50.0 1.89 1.87 EOC-RPT-OOS, 40.0 1.96 1.96 and PLUQOS 30.0 2.19 2.19 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at5<50%F 3.04 3.17 100.0 1.52 1.51 90.0 1.59 1.58 5 0 .0 ......
50.0 1.89 1.87 CROOS, 40.0 2.00 2.01 and PLUQOS 30.0 2.24 2.24 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.55 1.54 90.0 1.61 1.61 50.0 ---
50.0 1.89 1.90 TBVOOS, 40.0 2.03 2.04 and PLUQOS 30.0 2.27 2.27 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.55 1.54 90.0 1.61 1.61 5 0 .0 ......
EOC-RPT-OOS, 50.0 1.89 1.90 TBVOOS, 40.0 2.03 2.04 FHOOS, 30.0 2.27 2.27 and PLUOOS 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-7 Table 8.2 MCPRp Limits for TSSS Insertion Times BOC to NEOC*
MCPRP Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.53 1.52 90.0 1.58 1.58 50.0 1.80 1.81 50.0 1.85 1.84 Base case 40.0 1.94 1.94 operation 30.0 2.16 2.16 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 100.0 1.56 1.55 90.0 1.62 1.61 5 0 .0 ......
50.0 1.85 1.85 40.0 1.98 1.97 30.0 2.21 2.20 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at 5 50%F 2.71 2.83 25.0 at* 50%F 3.04 3.17 100.0 1.53 1.52 90.0 1.58 1.58 50.0 1.80 1.81 50.0 1.85 1.84 40.0 1.94 1.94 30.0 2.16 2.16 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 100.0 1.56 1.54 90.0 1.61 1.60 5 0 .0 ......
50.0 1.86 1.89 40.0 2.01 2.02 30.0 2.25 2.25 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96
- Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRP limits-will be 0.02 higher.
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Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-8 Table 8.2 MCPRp Limits for TSSS Insertion Times BOC to NEOC (Continued)
MCPRP Operating Power ATRIUM-10 GE14 Condition (%of rated) Fuel Fuel 100.0 1.53 1.52 90.0 1.58 1.58 5 0 .0 ......
50.0 1.89 1.87 40.0 1.94 1.94 30.0 2.16 2.16 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 100.0 1.56 1.55 90.0 1.62 1.61 50.0 --- ---
50.0 1.85 1.85 EOC-RPT-OOS 40.0 1.98 1.97 and TBVOOS 30.0 2.21 2.20 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at* 50%F 3.04 3.17 100.0 1.56 1.54 90.0 1.61 1.60 50 .0 ......
50.0 1.86 1.89 EOC-RPT-OOS 40.0 2.01 2.02 and FHOOS 30.0 2.25 2.25 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.53 1.52 90.0 1.58 1.58 50.0 ---
50.0 1.89 1.87 EOC-RPT-OOS 40.0 1.94 1.94 and PLUOOS 30.0 2.16 2.16 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-9 Table 8.2 MCPRp Limits for TSSS Insertion Times BOC to NEOC (Continued)
MCPRp Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.59 1.57 90.0 1.64 1.63 50 .0 ......
50.0 1.89 1.92 TBVOOS 40.0 2.05 2.05 and FHOOS 30.0 2.29 2.29 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.56 1.55 90.0 1.62 1.61 50 .0 ......
50.0 1.89 1.87 TBVOOS 40.0 1.98 1.97 and PLUOOS 30.0 2.21 2.20 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at < 50%F 3.04 3.17 100.0 1.56 1.54 90.0 1.61 1.60 50.0 ---
50.0 1.89 1.89 FHOOS 40.0 2.01 2.02 and PLUOOS 30.0 2.25 2.25 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.59 1.57 90.0 1.64 1.63 50 .0 ......
50.0 1.89 1.92 EOC-RPT-OOS, 40.0 2.05 2.05 TBVOOS, 30.0 2.29 2.29 and FHOOS 3. .922 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-10 Table 8.2 MCPRp Limits for TSSS Insertion Times BOC to NEOC (Continued)
MCPRP Operating Power ATRIUM-10 GE14 Condition (%of rated) Fuel Fuel 100.0 1.56 1.55 90.0 1.62 1.61 50.0 --- -
50.0 1.89 1.87 EOC-RPT-OOS, 40.0 1.98 1.97 and PLUQOS 30.0 2.21 2.20 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at5<50%F 3.04 3.17 100.0 1.56 1.54 90.0 1.61 1.60 5 0 .0 ......
50.0 1.89 1.89 EOC-RPT-OOS, 40.0 2.01 2.02 and PLUQOS 30.0 2.25 2.25
,30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.59 1.57 90.0 1.64 1.63 5 0 .0 ......
50.0 1.89 1.92 TBVOOS, 40.0 2.05 2.05 and PLUOOS 30.0 2.29 2.29 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.59 1.57 90.0 1.64 1.63 5 0 .0 ......
EOC-RPT-OOS, 50.0 1.89 1.92 TBVOOS, 40.0 2.05 2.05 FHOOS, 30.0 2.29 2.29 and PLUOOS 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-11 Table 8.3 MCPRp Limits for NSS Insertion Times BOC to EOCLB*
MCPRp Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.49 1.49 90.0 1.55 1.55 50.0 1.78 1.80 50.0 1.86 1.85 Base case 40.0 1.92 1.92 operation 30.0 2.15 2.15 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 100.0 1.52 1.52 90.0 1.58 1.58 5 0 .0 ......
50.0 1.86 1.85 40.0 1.96 1.96 30.0 2.19 2.19 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at:<50%F 3.04 3.17 100.0 1.49 1.49 90.0 1.55 1.55 50.0 1.78 1.80 50.0 1.86 1.85 40.0 1.92 1.92 30.0 2.15 2.15 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 100.0 1.52 1.51 90.0 1.59 1.58 5 0 .0 ......
50.0 1.86 1.87 FHOOS 40.0 2.00 2.01 30.0 2.24 2.24 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRp limits will be 0.02 higher.
AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision I Reload Safety Analysis for 105% OLTP Page 8-12 Table 8.3 MCPRp Limits for NSS Insertion Times BOC to EOCLB (Continued)
MCPRP Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.49 1.49 90.0 1.55 1.55 5 0 .0 ......
50.0 1.91 1.91 40.0 1.92 1.92 30.0 2.15 2.15 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 100.0 1.52 1.52 90.0 1.58 1.58 50.0 - ---
50.0 1.86 1.85 EOC-RPT-OOS 40.0 1.96 1.96 and TBVOOS 30.0 2.19 2.19 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at < 50%F 3.04 3.17 100.0 1.52 1.51 90.0 1.59 1.58 5 0 .0 .... ..
50.0 1.86 1.87 EOC-RPT-OOS 40.0 2.00 2.01 and FHOOS 30.0 2.24 2.24 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.49 1.49 90.0 1.55 1.55 5 0 .0 ......
50.0 1.91 1.91 EOC-RPT-OOS 40.0 1.92 1.92 and PLUOOS 30.0 2.15 2.15 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-13 Table 8.3 MCPRp Limits for NSS Insertion Times BOC to EOCLB (Continued)
MCPRp Operating Power ATRIUM-10 GE14 Condition (%of rated) Fuel Fuel 100.0 1.55 1.54 90.0 1.61 1.61 50 .0 . ... ..
50.0 1.87 1.90 TBVOOS 40.0 2.03 2.04 and FHOOS 30.0 2.27 2.27 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.52 1.52 90.0 1.58 1.58 5 0 .0 ......
50.0 1.91 1.91 TBVOOS 40.0 1.96 1.96 and PLUOOS 30.0 2.19 2.19 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at* 50%F 3.04 3.17 100.0 1.52 1.51 90.0 1.59 1.58 5 0 .0 ......
50.0 1.91 1.91 FHOOS 40.0 2.00 2.01 and PLUOOS 30.0 2.24 2.24 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.55 1.54 90.0 1.61 1.61 5 0 .0 ......
50.0 1.87 1.90 EOC-RPT-OOS, 40.0 2.03 2.04 TBVOOS, 30.0 2.27 2.27 and FHOOS 3. .722 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page*8-14 Table 8.3 MCPRp Limits for NSS Insertion Times BOC to EOCLB (Continued)'
MCPRP Operating Power ATRIUM-10 GE14 Condition (%of rated) Fuel Fuel 100.0 1.52 1.52 90.0 1.58 1.58 5 0 .0 ......
50.0 1.91 1.91 EOC-RPT-OOS, 40.0 1.96 1.96 and PLUQOS 30.0 2.19 2.19 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at5 50%F 3.04 3.17 100.0 1.52 1.51 90.0 1.59 1.58 5 0 .0 ......
50.0 1.91 1.91 EOC-RPT-OOS, 40.0 2.00 2.01 and PLU00S 30.0 2.24 2.24 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.55 1.54 90.0 1.61 1.61 50 .0 .... ..
50.0 1.91 1.91 TBVOOS, 40.0 2.03 2.04 and PLUOOS 30.0 2.27 2.27 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.55 1.54 90.0 1.61 1.61 50 .0 ......
EOC-RPT-OOS, 50.0 1.91 1.91 TBVOOS, 40.0 2.03 2.04 FHOOS, 30.0 2.27 2.27 and PLUOOS 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-15 Table 8.4 MCPRP Limits for TSSS Insertion Times BOC to EOCLB*
MCPRp Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.53 1.52 90.0 1.58 1.58 50.0 1.80 , 1.81 50.0 1.87 1.85 Base case 40.0 1.94 1.94 operation 30.0 2.16 2.16 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at 5 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 100.0 1.56 1.55 90.0 1.62 1.61 5 0.0 ......
50.0 1.87 1.85 TBVOOS 40.0 1.98 1.97 30.0 2.21 2.20 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at* 50%F 3.04 3.17 100.0 1.53 1.52 90.0 1.58 1.58 50.0 1.80 1.81 50.0 1.87 1.85 40.0 1.94 1.94 30.0 2.16 2.16 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at : 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 100.0 1.56 1.54 90.0 1.61 1.60 5 0 .0 . ... ..
50.0 1.87 1.89 40.0 2.01 2.02 FHOOS 30.0 2.25 2.25 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96
- Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. For single-loop operation, MCPRP limits will be 0.02 higher.
AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-16 Table 8.4 MCPRp Limits for TSSS Insertion Times BOC to EOCLB (Continued)
MCPRp Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.53 1.52 90.0 1.58 1.58 50 .0 ......
50.0 1.91 1.91 40.0 1.94 1.94 30.0 2.16 2.16 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 100.0 1.56 1.55 90.0 1.62 1.61 50.0 ...
50.0 1.87 1.85 EOC-RPT-OOS 40.0 1.98 1.97 and TBVOOS 30.0 2.21 2.20 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at* 50%F 3.04 3.17 100.0 1.56 1.54 90.0 1.61 1.60 50 .0 ......
50.0 1.87 1.89 EOC-RPT-OOS 40.0 2.01 2.02 and FHOOS 30.0 2.25 2.25 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.53 1.52 90.0 1.58 1.58 50 .0 ......
50.0 1.91, 1.91 EOC-RPT-OOS 40.0 1.94 1.94 and PLUOOS 30.0 2.16 2.16 30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at < 50%F 2.53 2.65 25.0 at < 50%F 2.72 2.83 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-17 Table 8.4 MCPRP Limits for TSSS Insertion Times BOC to EOCLB (Continued)
MCPRP Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.59 1.57 90.0 1.64 1.63 5 0 .0 .. .. ..
50.0 1.89 1.92 TBVOOS 40.0 2.05 2.05 and FHOOS 30.0 2.29 2.29 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.56 1.55 90.0 1.62 1.61 5 0 .0 ......
50.0 1.91 1.91 TBVOOS 40.0 1.98 1.97 and PLUOOS 30.0 2.21 2.20 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at* 50%F 3.04 3.17 100.0 1.56 1.54 90.0 1.61 1.60 50.0 ---
50.0 1.91 1.91 FHOOS 40.0 2.01 2.02 and PLUOOS 30.0 2.25 2.25 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.59 1.57 90.0 1.64 1.63 50.0 50.0 1.89 1.92 EOC-RPT-OOS, 40.0 2.05 2.05 and FHOOS 30.0 2.29 2.29 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-18 Table 8.4 MCPRp Limits for TSSS Insertion Times BOC to EOCLB (Continued)
MCPRp' Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.56 1.55 90.0 1.62 1.61 5 0 .0 ......
50.0 1.91 1.91 EOC-RPT-OOS, 40.0 1.98 1.97 and PLUQOS 30.0 2.21 2.20 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at < 50%F 2.71 2.83 25.0 at < 50%F 3.04 3.17 100.0 1.56 1.54 90.0 1.61 1.60 5 0 .0 ......
50.0 1.91 1.91 EOC-RPT-OOS, 40.0 2.01 2.02 FHOOS, 30.0 2.25 2.25 and PLUOOS 30.0 at3.> 50%F .522 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.59 1.57 90.0 1.64 1.63 5 0 .0 ......
50.0 1.91 1.92 TBVOOS, 40.0 2.05 2.05 FHOOS, and PLUOOS 30.0 2.29 2.29 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.59 1.57 90.0 1.64 1.63 5 0 .0 ......
EOC-RPT-OOS, 50.0 1.91 1.92 TBVOOS, 40.0 2.05 2.05 FHOOS, 30.0 2.29 2.29 and PLUOOS 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-19 Table 8.5 MCPRp Limits for NSS Insertion Times BOC to FFTR/Coastdown*
MCPRp Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.52 1.51 90.0 1.59 1.58 50.0 ---
50.0 1.86 1.87 Base case 40.0 2.00 2.01 operation 30.0 2.24 2.24 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.55 1.54 90.0 1.61 1.61 50 .0 ......
50.0 1.87 1.90 40.0 2.03 2.04 30.0 2.27 2.27 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.52 1.51 90.0 1.59 1.58 50 .0 ......
50.0 1.86 1.87 40.0 2.00 2.01 30.0 2.24 2.24 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. Limits also support operation with FFTR/FHOOS which bounds operation with feedwater heaters in-service. For single-loop operation, MCPRp limits will be 0.02 higher.
AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-20 Table 8.5 MCPRp Limits for NSS Insertion Times BOC to FFTR/Coastdown (Continued)
MCPRP Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.52 1.51 90.0 1.59 1.58 50 .0 ......
50.0 1.92 1.91 PLUOOS 40.0 2.00 2.01 30.0 2.24 2.24 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.55 1.54 90.0 1.61 1.61 5 0 .0 ......
50.0 1.87 1.90 EOC-RPT-OOS 40.0 2.03 2.04 and TBVOOS 30.0 2.27 2.27 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.52 1.51 90.0 1.59 1.58 50 .0 ......
50.0 1.92 1.91 EOC-RPT-OOS 40.0 2.00 2.01 and PLUOOS 30.0 2.24 2.24 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-21 Table 8.5 MCPRp Limits for NSS Insertion Times BOC to FFTR/Coastdown (Continued)
MCPRP Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.55 1.54 90.0 1.61 1.61 50.0 .. .
50.0 1.92 1.91 TBVOOS 40.0 2.03 2.04 and PLUOOS 30.0 2.27 2.27 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.55 1.54 90.0 1.61 1.61 5 0 .0 ......
50.0 1.92 1.91 EOC-RPT-OOS,. 40.0 2.03 2.04 TBVOOS, 30.0 2.27 2.27 and PLUOOS 3. .722 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-22 Table 8.6 MCPRp Limits for TSSS Insertion Times BOC to FFTR/Coastdown*
MCPRP Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.56 1.54 90.0 1.61 1.60 50.0 ---
50.0 1.87 1.89 Base case 40.0 2.01 2.02 operation 30.0 2.25 2.25 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.59 1.57 90.0 1.64 1.63 5 0 .0 ......
50.0 1.89 1.92 40.0 2.05 2.05 30.0 2.29 2.29 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.56 1.54 90.0 1.61 1.60 5 0 .0 ......
50.0 1.87 1.89 40.0 2.01 2.02 30.0 2.25 2.25 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. Limits also support operation with FFTR/FHOOS which bounds operation with feedwater heaters in-service. For single-loop operation, MCPRp limits will be 0.02 higher.
AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-23 Table 8.6 MCPRp Limits for TSSS Insertion Times BOC to FFTR/Coastdown (Continued)
MCPRp Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.56 1.54 90.0 1.61 1.60 5 0 .0 ......
50.0 1.92 1.91 40.0 2.01 2.02 30.0 2.25 2.25 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 100.0 1.59 1.57 90.0 1.64 1.63 50 .0 ......
50.0 1.89 1.92 EOC-RPT-OOS 40.0 2.05 2.05 and TBVOOS 30.0 2.29 2.29 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.56 1.54 90.0 1.61 1.60 5 0 .0 ......
50.0 1.92 1.91 EOC-RPT-OOS 40.0 2.01 2.02 and PLUOOS 30.0 2.25 2.25 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at < 50%F 2.62 2.75 25.0 at < 50%F 2.84 2.96 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-24 Table 8.6 MCPRp Limits for TSSS Insertion Times BOC to FFTR/Coastdown (Continued)
MCPRP Operating Power ATRIUM-10 GE14 Condition (% of rated) Fuel Fuel 100.0 1.59 1.57 90.0 1.64 1.63 5 0 .0 ......
50.0 1.92 1.92 TBVOOS 40.0 2.05 2.05 and PLUOOS 30.0 2.29 2.29 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 100.0 1.59 1.57 90.0 1.64 1.63 5 0 .0 ......
50.0 1.92 1.92 EOC-RPT-OOS, 40.0 2.05 2.05 TBVOOS, 30.0 2.29 2.29 and PLUOOS 3. .922 30.0 at > 50%F 3.13 3.17 25.0 at > 50%F 3.47 3.47 30.0 at < 50%F 2.82 2.95 25.0 at < 50%F 3.20 3.35 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-25 Table 8.7 Flow-Dependent MCPR Limits ATRIUM-10and GE14 Fuel Core Flow
(% of rated) MCPRf 30.0 1.61 78.0 1.28 107.0 1.28 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-26 Table 8.8 ATRIUM-10 Steady-State LHGR Limits Peak Pellet Exposure LHGR (GWd/MTU) (kW/ft) 0.0 13.4 18.9 13.4 74.4 7.1 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-27 Table 8.9 ATRIUM-10 LHGRFACp Multipliers for NSS/TSSS Insertion Times All Cycle 9 Exposures*
EOOS Power ATRIUM-10 Condition (% rated) LHGRFACP 100.0 1.00 Base 30.0 0.64 case 30.0 at > 50%F 0.47 operation 25.0 at > 50%F 0.47 (TBVIS) 30.0 at < 50%F 0.47 25.0 at < 50%F 0.47 100.0 0.90 90.0 0.83 30.0 0.62 TBVOOSI 30.0 at > 50%F 0.43 25.0 at > 50%F 0.39 30.0 at < 50%F 0.47 25.0 at < 50%F 0.46
- Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. Base case supports single-loop operation.
t Limits are applicable for all the EOOS scenarios presented in Table 1.1 except those that include TBVOOS.
- Limits are applicable for all the EOOS scenarios presented in Table 1.1 including those with TBVOOS.
AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-28 Table 8.10 GE14 LHGRFACp Multipliers for NSS/TSSS Insertion Times All Cycle 9 Exposures*
EOOS Power GE14 Condition (% rated) LHGRFACp 100.0 1.00 75.0 0.78 Base case 30.0 0.60 operation 30.0 at > 50%F 0.44 (TBVIS)t 25.0 at > 50%F 0.42 30.0 at < 50%F 0.44 25.0 at < 50%F 0.44 100.0 0.99 75.0 0.77 30.0 0.58 TBVOOS* 30.0 at > 50%F 0.37 25.0 at > 50%F 0.31 30.0 at < 50%F 0.44 25.0 at < 50%F 0.43 Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service. Base case supports single-loop operation.
t Limits are applicable for all the EOOS scenarios presented in Table 1.1 except those that include TBVOOS.'
Limits are applicable for all the EOOS scenarios presented in Table 1.1 including those with TBVOOS.
AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-29 Table 8.11 ATRIUM-10 LHGRFACf Multipliers All Cycle 9 Exposures Core Flow
(% of rated) LHGRFACf 0.0 0.86 30.0 0.86 56.4 1.00 107.0 1.00 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-30 Table 8.12 GE14 LHGRFACf Multipliers All Cycle 9 Exposures Core Flow GE14
(% rated) LHGRFACf 0.0 0.54 30.0 0.54 81.8 1.00 107.0 1.00 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 8-31 Table 8.13 ATRIUM-10 MAPLHGR Limits Average Planar Exposure MAPLHGR (GWd/MTU) (kW/ft) 0.0 12.5 15.0 12.5 67.0 7.3 AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 9-1 9.0 References
- 1. ANP-2859(P) Revision 1, Browns Ferry Unit 1 Cycle 9 Fuel Cycle Design (105% OLTP),
AREVA NP, October 2009.
- 2. AN P-2877(P) Revision 0, MechanicalDesign Report for Browns Ferry Unit 1 Reload BFEI-9 ATRIUM-1O Fuel Assemblies (105% OLTP), AREVA NP, November 2009.
- 3. ANP-2821 (P) Revision 0, Browns Ferry Unit 1 Thermal-HydraulicDesign Report for ATRIUM* m-10 Fuel Assemblies (105% OLTP), AREVA NP, June 2009.
- 4. ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF Critical PowerMethodology for Boiling Water Reactors,Advanced Nuclear Fuels Corporation, November 1990.
- 5. EMF-2209(P)(A) Revision 3, SPCB CriticalPower Correlation,AREVA NP, September 2009.
- 6. EMF-2245(P)(A) Revision 0, Application of Siemens PowerCorporation'sCriticalPower Correlationsto Co-Resident Fuel, Siemens Power Corporation, August 2000.
- 7. NEDO-32465-A, Licensing Topical Report, Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications, GE Nuclear Energy, August 1996.
- 8. OG04-0153-260, Plant-Specific Regional Mode DIVOM Procedure Guideline, June 15, 2004.
- 9. BWROG-03047, Resolution of Reportable Condition for Stability Reload Licensing Calculations Using Generic Regional Mode DIVOM Curve, September 30, 2003.
- 10. OG02-0119-260, Backup Stability Protection (BSP) for Inoperable Option III Solution, GE Nuclear Energy, July 17, 2002.
- 11. EM F-CC-074(P)(A) Volume 4 Revision 0, BWR Stability Analysis - Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.
- 12. ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Programfor Boiling Water Reactor TransientAnalyses, Advanced Nuclear Fuels Corporation, August 1990.
13.. XN-NF-84-105(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-HydraulicCore Analysis, Exxon Nuclear Company, February 1987.
- 14. 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.
AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 9-2
- 15. EM F-2158(P)(A) Revision 0, Siemens Power CorporationMethodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, Siemens Power Corporation, October 1999.
- 16. XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-MechanicalResponse Evaluation Model, Exxon Nuclear Company, March 1984.
- 17. Technical Specification Requirements for Browns Ferry Nuclear Plant Unit 1, Tennessee Valley Authority, as amended.
- 18. ANF-1 358(P)(A) Revision 3, The Loss of FeedwaterHeating Transientin Boiling Water Reactors, Framatome ANP, September 2005.
- 19. ANP-2908(P) Revision 0, Browns Ferry Units 1, 2, and 3 105% OLTP LOCA Break Spectrum Analysis, AREVA NP, March 2010.
- 20. ANP-2910(P) Revision 0, Browns Ferry Units 1, 2, and 3 105% OLTP LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM TM-1O Fuel, AREVA NP, March 2010.
- 21. 0000-0044-1520-SRLR Revision 0, Supplemental Reload Licensing Report for Browns Ferry I Reload 6 Cycle 7, Global Nuclear Fuel, January 2007.
- 22. 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.
- 23. 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.
- 24. EMF-2978(P) Revision 0, Browns FerryNuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUMm-10 Fuel, Framatome ANP, July 2005.
- 25. EMF-2939(P) Revision 0, Browns Ferry Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for ATRIUMTM-10 Fuel, Framatome ANP, August 2003.
- 26. 0000-0077-8380-SRLR Revision 0, Supplemental Reload Licensing Report for Browns Ferry I Reload 7 Cycle 8, Global Nuclear Fuel, August 2008.
- 27. Letter, EA Brown (NRC) to KW Singer (TVA), "Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendments Regarding Full-Scope Implementation of Alternative Source Term (TAC Nos. MB5733, MB5734, MB5735, MC0156, MC0157 and MC0158)
(TS-405)," September 27, 2004.
- 28. Letter, TA Galioto (FANP) to JF Lemons (TVA), "Fuel Handling Accident Assumptions for Browns Ferry," TAG:02:012, January 23, 2002.
MJM-TVA-ER1-09-39, April 2, 2009.
- 30. BAW-1 0255PA Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, AREVA NP, May 2008.
AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page 9-3
- 31. Not used.
- 32. ANP-2860(P) Revision 2, Browns Ferry Unit 1 - Summary of Responses to Request for Additional Information, AREVA NP, October 2009.
Proposed Technical Specifications (TS) Change TS - 431 - Request for License Amendment - Extended Power Uprate (EPU) Operation," TVA-BFN-TS-431, June 28, 2004.
- 34. EMF-2982(P) Revision 0, Browns Ferry Units 2 and 3 Safety Analysis Report for Extended Power Uprate ATRIUM TM-1O Fuel Supplement, Framatome ANP, June 2004.
- 35. NEDC-33047P Revision 2, Browns Ferry Units 2 and 3 Safety Analysis Report for Extended Power Uprate, GE Nuclear Energy, June 2004.
- 36. NEDO-33101, Browns Ferry Unit 1 Safety Analysis Report ForExtended Power Uprate, GE Nuclear Energy, June 2004.
- 37. Browns Ferry Nuclear Plant Units 1, 2, and 3 Fire ProtectionReport Volume I Section 3 Safe Shutdown Analysis, Revision 4, Tennessee Valley Authority, March 25, 2009.
- 39. ANP-2638(P), Revision 2, Applicability of AREVA NP BWR Methods to Extended Power Uprate Conditions,AREVA NP Inc., October 2009.
- 40. Letter, S Richards (NRC) to JF Mallay (SPC), "Siemens Power Corporation Re: Request for Concurrence on Safety Evaluation Report Clarifications (TAC No. MA6160)," May 31, 2000.
AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-1 Appendix A Operating Limits and Results Comparisons The figures and tables presented in this appendix show comparisons of the BF1 Cycle 9 operating limits and the transient analysis results. Comparisons are presented for the ATRIUM-10 and GE14 MCPRp limits and LHGRFACp multipliers.
AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-2 3.0 o FWCF o LRNB A CRWE 2.5 I-E 0
o_ 2.0 0 a_
0 1.5 1- 0 0
1.0 i 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.49 90 1.55 50 1.78 50 1.84 40 1.92 30 2.15 30 at > 50%F 2.56 25 at > 50%F 2.77 30 at < 50%F 2.53 25 at* 50%F 2.72 Figure A.1 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times Base Case AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-3 3.0 0 FWCF o LRNB a CRWE 2.5 1-E 0
0- 2.0 P 0
o 1.5 1 A A 0 0 0 0
III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.49 90 1.55 50 1.80 50 1.83 40 1.92 30 2.15 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at5<50%F 2.65 25 at 5 50%F 2.83 Figure A.2 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times Base Case AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-4 3.0 o FWCF o LRNB
- CRWE 2.5
__j 0
2.0 CL 0~
C-)
- 7. 0 AA 1.5 0 6 0
1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.49 90 1.55 50 1.78 50 1.86 40 1.92 30 2.15 30 at > 50%F 2.56 25 at > 50%F 2.77 30 at < 50%F 2.53 25 at5 50%F 2.72 Figure A.3 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times Base Case AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-5 3.0 I I I I I I I 0 FWCF 0 LRNB A CRWE 2.5 k
-j 0 CL 2.0 0
0y n-1.5 1-0I 0 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.49 90 1.55 50 1.80 50 1.85 40 1.92 30 2.15 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at:<50%F 2.65 25 at < 50%F 2.83 Figure A.4 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times Base Case AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-6 3.5 o FWCF o LRNB 3.0 A CRWE 4E 2.5 0d 0_
0 0
2.0 0 0
00 1.5 o A 6 6 ii I i I i I i 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 1.59 50 50 1.86 40 2.00 30 2.24 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at <- 50%F 2.62 25 at < 50%F 2.84 Figure A.5 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-I1 Fuel NSS Insertion Times Base Case AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-7 3.5 o FWCF o" LRNB 3.0 CRWE 2.5 n~
0~ 0 02 2.0 0 0 A
1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.51 90 1.58 50 ---
50 1.87 40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at5<50%F 2.75 25 at:<50%F 2.96 Figure A.6 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times Base Case AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision I Reload Safety Analysis for 105% OLTP . Page A-8 3.0 o FWCF
.o LRNB A CRWE 2.5 1-EJ 0
_j 0 2.0 1-a~
0A 1.5 1- o a. o 0I I0 6 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.53 90 1.58 50 1.80 50 1.85 40 1.94 30 2.16 30 at > 50%F 2.56 25 at > 50%F 2.77 30 at:<50%F 2.53 25 at < 50%F 2.72 Figure A.7 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times Base Case AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-9 3.0 3 FWCF o LRNB S CRWE 2.5 E
IJ 0 2.0 k 0
CL)
A 0 1.5 t- A A 0 0 I 0
1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.58 50 1.81 50 1.84 40 1.94 30 2.16 30 at > 50%F 2.65 25 at> 50%F 2.86 30 at5<50%F 2.65 25 at < 50%F 2.83 Figure A.8 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times Base Case AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-10 3.0
- FWCF o LRNB
- CRWE 2.5 E
0 cL 2.0 0 a:_
(3.
0J AA 1.5 1-0 o 00 I I II I0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.53 90 1.58 50 1.80 50 1.87 40 1.94 30 2.16 30 at > 50%F 2.56 25 at > 50%F 2.77 30 at5<50%F 2.53 25 at5<50%F 2.72 Figure A.9 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times Base Case AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-11 3.0 o FWCF o LRNB A CRWE 2.5 E
0
_ 2.0 0 0n C3_
0 1.5 1-0 00 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.58 50 1.81 50 1.85 40 1.94 30 2.16 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at5<50%F 2.65 25 at* 50%F 2.83 Figure A.1O BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times Base Case AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-12 3.5
[] FWCF o LRNB 3.0 A CRWE 2.5 2E
._J 0
S2.0 0 0
1.5 F 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.56 90 1.61 50 ---
50 1.87 40 2.01 30 2.25 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at5<50%F 2.62 25 at5<50%F 2.84 Figure A.11 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times Base Case AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-13 3.5 0 FWCF 0 LRNB 3.0 A CRWE 2.5 0:ý n~ 0 2.0 1 0 AA A
1.5 [
III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.60 50 ---
50 1.89 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at5<50%F 2.75 25 at < 50%F 2.96 Figure A.12 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times Base Case AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-14 3.5 3.0 2.5
-4 2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.84 40 1.96 30 2.19 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at:<50%F 2.71 25 at < 50%F 3.04 Figure A.13 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times TBVOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-15 3.5 0 FWCF 0 LRNB 3.0 A CRWE 2.5 41 a-2.0 o 0
1.5 II I II I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.83 40 1.96 30 2.19 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at:<50%F 2.83 25 at5<50%F 3.17 Figure A.14 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times TBVOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-16 3.5 o FWCF o LRNB 3.0 a CRWE 2.5 a-0 2.0 0 6 1.5 1-III I I I I I" I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.86 40 1.96 30 2.19 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at < 50%F 2.71 25 at < 50%F 3.04 Figure A.15 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times TBVOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-17 3.5 o FWCF o LRNB 3.0
- CRWE
.E 2.5
-j 0- 0 2.0 0
A 0
A 1.5 0 0 I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.85 40 1.96 30 2.19 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at5<50%F 2.83 25 at5<50%F 3.17 Figure A.16 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times TBVOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-18 4.0 o FWCF o LRNB 3.5 A CRWE 3.0
- t-E a- 2.5 0~
02 0
0 0 2.0 00 oA 1.5 III I I I I I I I "
1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.87 40 2.03 30 2.27
%30at > 50%F 3.13 25 at > 50%F 3.47 30 at5<50%F 2.82 25 at < 50%F 3.20 Figure A.17 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times TBVOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-19 4.0 III O FWCF o LRNB 3.5 A CRWE 3.0
-J 2.5 0ý 0
2.0 A 0 1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.54 90 1.61 50 ---
50 1.90 40 2.04 30 2.27 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at* 50%F 2.95 25 at* 50%F 3.35 Figure A.18 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times TBVOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-20 3.5 o] FWCF o LRNB 3.0
- CRWE 2.5
-j 01 0 0
2.0 0 0
A 0 0 AA 1.5 0 A 0 0 I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.56 90 1.62 50 50 1.85 40 1.98 30 2.21 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at* 50%F 2.71 25 at* 50%F 3.04 Figure A.19 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times TBVOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-21 3.5 3.0 2.5
-J CL 0~~
0 2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.85 40 1.97 30 2.20 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at* 50%F 2.83 25 at5<50%F 3.17 Figure A.20 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times TBVOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-22 3.5 0 FWCF o LRNB 3.0 a CRWE 2.5 41 ry 0
- n. 0 2.0 0 0
A A 0 1.5 0 0 i i i ii i i 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.56 90 1.62 50 ---
50 1.87 40 1.98 30 2.21 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at < 50%F 2.71 25 at* 50%F 3.04 Figure A.21 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times TBVOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-23 3.5 o FWCF o LRNB A CRWE 3.0 2.5 CL x~
a- 0 0
2.0 0 o A0 A 1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.85 40 1.97 30 2.20 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at5<50%F 2.83 25 at5<50%F 3.17 Figure A.22 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times TBVOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-24 4.0 0 FWCF o LRNB 3.5 A CRWE 3.0 Ej 2.5 0n 0
0 0 2.0 00 A A
, A 1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP-(% of rated) Limit 100 1.59 90 1.64 50 ---
50 1.89 40 2.05 30 2.29 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at5<50%F 2.82 25 at < 50%F 3.20 Figure A.23 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times TBVOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-25 4.0 IIIIIIII 0 FWCF o LRNB 3.5 A CRWE 3.0
-E
__j 2.5 a_~
0 2.0 0 00 0A 1.5 0 6 I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.57 90 1.63 50 ---
50 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at* 50%F 2.95 25 at < 50%F 3.35 Figure A.24 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times TBVOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-26 3.0 o3 FWCF o LRNB A CRWE 2.5 k E 0
-j 2.0 1- 0 C) 1.5 1-0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.49 90 1.55 50 1.78 50 1.84 40 1.92 30 2.15 30 at > 50%F 2.56 25 at > 50%F 2.77 30 at:<50%F 2.53 25 at < 50%F 2.72 Figure A.25 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-27 3.0 n FWCF 0 LRNB A CRWE 2.5 1-
-- I 0 2.0 P 0
0 Ao A
1.5 [- AA A
0 0 o 0
1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.49 90 1.55 50 1.80 50 1.83 40 1.92 30 2.15 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at* 50%F 2.65 25 at5<50%F 2.83 Figure A.26 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-28 3.0 IIII I I ol FWCF o LRNB A CRWE 2.5 1-
- t 0
2.0 1- 0 0-)
1.5 k 0
1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.49 90 1.55 50 1.78 50 1.86 40 1.92 30 2.15 30 at > 50%F 2.56 25 at > 50%F 2.77 30 at < 50%F 2.53 25 at* 50%F 2.72 Figure A.27 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-29 3.0 o[ FWCF o LRNB A CRWE 2.5 1
-j 0
CL 2.0 1 0
(if n
AA 1.5 1- A A 0 0 5 0
1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.49 90 1.55 50 1.80 50 1.85 40 1.92 30 2.15 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at5<50%F 2.65 25 at < 50%F 2.83 Figure A.28 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-30 3.5 3.0
- 2.5 a-2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.59 50 ---
50 1.86 40 2.00 30 2.24 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at* 50%F 2.62 25 at < 50%F 2.84 Figure A.29 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-31 3.5 3.0 E 2.5
-j n-)
2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.51 90 1.58 50 ---
50 1.87 40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at5<50%F 2.75 25 at < 50%F 2.96 Figure A.30 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-32 3.0 2.5 E
-J C_ 2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.53 90 1.58 50 1.80 50 1.85 40 1.94 30 2.16 30 at > 50%F 2.56
.25 at > 50%F 2.77 30 at < 50%F 2.53 25 at5<50%F 2.72 Figure A.31 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-33 3.0 0 FWCF o LRNB A CRWE 2.5 1
- t 0 2.0 F C-) 0 A
A A 1.5 -
0 0 0 0
III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.58 50 1.81 50 1.84 40 1.94 30 2.16 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at* 50%F 2.65 25 at* 50%F 2.83 Figure A.32 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-34 3.0 o FWCF o LRNB a CRWE 2.5 Ej 0 I~
2.0 k 0 0L 1.5 1- 00 0 A 0 I II I II I I0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.53 90 1.58 50 1.80 50 1.87 40 1.94 30 2.16 30 at > 50%F 2.56 25 at > 50%F 2:77 30 at* 50%F 2.53 25 at* 50%F 2.72 Figure A.33 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-35 3.0 I I *'II 0 FWCF o LRNB A CRWE 2.5 I-
- t 0
E~ 2.0 [- 0 C) 0 0 AA 1.5 [
o 00 I II II II0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.58 50 1.81 50 1.85 40 1.94 30 2.16 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at5<50%F 2.65 25 at* 50%F 2.83 Figure A.34 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-36 3.5 O FWCF o LRNB 3.0 a CRWE 2.5 01 0 0
2.0 0 1.5 0 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.56 90 1.61 50 50 1.87 40 2.01 30 2.25 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at5<50%F 2.62 25 at5<50%F 2.84 Figure A.35 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times
- EOC-RPT-OOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-37 3.5 O3 FWCF o LRNB 3.0 A CRWE 2.5 41 0y q~ 0 2.0 0 0 A 1.5 1 A SII I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.54 90 1.60 50 ---
50 1.89 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at < 50%F 2.75 25 at < 50%F 2.96 Figure A.36 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-38 3.5 I I i i I I o FWCF o LRNB 3.0 I-
- CRWE 2.5 H
-J 0
2.0 I- 0 0
a A
A*
1.5 1.0 I I I I. I I I I I 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.59 50 ---
50 1.84 40 2.00 30 2.24 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at < 50%F 2.62 25 at < 50%F 2.84 Figure A.37 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times FHOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-39 3.5 IIIIII I o FWCF 0 LRNB 3.0 1- A CRWE 2.5 [
41 0
2.0 0 AA 1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.51 90 1.58 50 ---
50 1.87 40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at < 50%F 2.75 25 at:<50%F 2.96 Figure A.38 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times FHOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-40 3.5 o1 FWCF o LRNB 3.0
- CRWE 2.5 0y n~ 0 2.0 0 (0
1.5 0 6 6 I A I 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 1.59 50 ---
50 1.86 40 2.00 30 2.24 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at:<50%F 2.62 25 at* 50%F 2.84 Figure A.39 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times FHOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-41 3.5 O FWCF o LRNB 3.0 A CRWE 2.5 41 C-)
0 2.0 0
AA 1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.51 90 1.58 50 50 1.87 40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at5<50%F 2.75 25 at5<50%F 2.96 Figure A.40 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times FHOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-42 3.5 O3 FWCF o LRNB 3.0 " CRWE
- 2.5
°r_
2 02.
0
- 2.0 0 0
1.5 F- 06 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.56 90 1.61 50 50 1.86 40 2.01 30 2.25 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at* 50%F 2.62 25 at* 50%F 2.84 Figure A.41 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times FHOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-43 3.5 IIIIIII I o FWCF o LRNB 3.0 A CRWE 2.5 0~
a:
0~ 0 C~)
2.0 A A 1.5 I I I I I I I
III 1.0 I I I I 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.54 90 1.60 50 ---
50 1.89 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at:<50%F 2.75 25 at5<50%F 2.96 Figure A.42 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times FHOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-44 3.5 o FWCF o LRNB 3.0 a CRWE 41 n-0 0
2.0 0 o0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.56 90 1.61 50 50 1.87 40 2.01 30 2.25 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at < 50%F 2.62 25 at < 50%F 2.84 Figure A.43 BOC to EOCLB Power-Dependent MCPR, Limits for ATRIUM-10 Fuel TSSS Insertion Times
. FHOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-45 3.5 o FWCF o LRNB 3.0 1- A CRWE _
2.5 F 41 n~ 0 2.0 F 0 1.5 1- o 6 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.60 50 ---
50 1.89 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at < 50%F 2.75 25 at:<50%F 2.96 Figure A.44 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times FHOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-46 3.0 o3 FWCF o LRNB A CRWE 2.5 1-0
-J 2.0 0 C) 0 I 1.5 0 IA 6 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.49 90 1.55 50 ---
50 1.89 40 1.92 30 2.15 30 at > 50%F 2.56 25 at > 50%F 2.77 30 at < 50%F 2.53 25 at* 50%F 2.72 Figure A.45 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times PLUOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-47 3.0 o1 FWCF o LRNB A CRWE 2.5 41 0
CL 2.0 0
0y_
n A o.
0 1.5 o 6 1.0 i i M i i 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.49 90 1.55 50 ---
50 1.87 40 1.92 30 2.15 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at* 50%F 2.65 25 at < 50%F 2.83 Figure A.46 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times PLUOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-48 3.0 o3 FWCF o LRNB A CRWE 2.5 1-
- t 0 2.0 1- 0 0~
- )
03 0 1.5 1-I II .3 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.49 90 1.55 50 ---
50 1.91 40 1.92 30 2.15 30 at > 50%F 2.56 25 at > 50%F 2.77
-30 at* 50%F 2.53 25 at* 50%F 2.72 Figure A.47 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times PLUOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-49 3.0 I III o FWCF o LRNB A CRWE 2.5 F
-j 0 CL 2.0 F 0
Of a_ 00
[] 0 A
Ai 1.5 F 1.0 i 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.49 90 1.55 50 ---
50 1.91 40 1.92 30 2.15 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at5<50%F 2.65 25 at < 50%F 2.83 Figure A.48 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times PLUOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-50 3.5 o FWCF o LRNB 3.0 A CRWE 2.5 a-0 2.0 0 00 0 0 1.5 1- A 0 Q 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 1.59 50 ---
50 1.92 40 2.00 30 2.24 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at5<50%F 2.62 25 at < 50%F 2.84 Figure A.49 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-1O Fuel NSS Insertion Times PLUOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-51 3.5 3.0 2.5 a_
2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.51 90 1.58 50 ---
50 1.91 40 2.01 30 2.24 30 at > 50%F 2.76 25 at >.50%F 3.00 30 at* 50%F 2.75 25 at:<50%F 2.96 Figure A.50 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times PLUOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-52 3.0 2.5 E
CL 2.0 rY 1.5 1.0 0 10 20 30 4-0 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.53 90 1.58 50 ---
50 1.89 40 1.94 30 2.16 30 at > 50%F 2.56 25 at > 50%F 2.77 30 at < 50%F 2.53 25 at5<50%F 2.72 Figure A.51 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times PLUOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-53 3.0 o FWCF o LRNB A CRWE 2.5 F
-j 0
0- 2.0 F 0
0~
- )
1.5 F 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.87 40 1.94 30 2.16 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at < 50%F 2.65 25 at5<50%F 2.83 Figure A.52 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times PLUOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-54 3.0 ol FWCF o LRNB A CRWE 2.5 [
- t 0
E~
2.0 F 0 0y 0A 0A 1.5 F S2 I I f !!II t I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.53 90 1.58 50 ---
50 1.91 40 1.94 30 2.16 30 at > 50%F 2.56 25 at > 50%F 2.77 30 at < 50%F 2.53 25 at < 50%F 2.72 Figure A.53 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times PLUOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety'Analysis for 105% OLTP Page A-55 3.0 I III I I O FWCF o LRNB A CRWE 2.5 1-E
-- I 0 0
cL 2.0 0L o0
- 0) S 0 0
[] 0 0A
- 0 6 6 1.5 I-1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 .1.58 50 ---
50 1.91 40 1.94 30 2.16 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at5<50%F 2.65 25 at* 50%F 2.83 Figure A.54 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times PLUOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-56 3.5 3.0 2.5
-J 2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.56 90 1.61 50 ---
50 1.92 40 2.01 30 2.25 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at < 50%F 2.62 25 at < 50%F 2.84 Figure A.55 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-1O Fuel TSSS Insertion Times PLUOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-57 3.5 o FWCF o LRNB 3.0 1- A CRWE 2.5 1 0~ 0
- 2 0 0 2.0 F- 0 1.5 [- 6 A 6 IIII I I I I II 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.60 50 50 1.91 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at < 50%F 2.75 25 at* 50%F 2.96 Figure A.56 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times PLUOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-58 3.5 o FWCF o LRNB 3.0 A CRWE 2.5
¢-y 2.0 0
S2.0 0 0
A 0 A0 1.5 1 0 6 II I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.84 40 1.96 30 2.19 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at5<50%F 2.71 25 at5<50%F 3.04 Figure A.57 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS and TBVOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-59 3.5 I I I I I I o FWCF o LRNB 3.0 A CRWE 2.5 Q-CL
- a. 0 2.0 A
1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.83 40 1.96 30 2.19 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at* 50%F 2.83 25 at 5 50%F 3.17 Figure A.58 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS and TBVOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-60 3.5 o FWCF o LRNB 3.0 A CRWE
.E 2.5
-j 0-Or) 2.0 0 A
1.5 o A 8 6 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.86 40 1.96 30 2.19 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at* 50%F 2.71 25 at s 50%F 3.04 Figure A.59 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS and TBVOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-61 3.5 3 FWCF o LRNB 3.0 k- A CRWE 2.5 [
41 0~ 0 02 2.0 [
0 AA 1.5 l- 0A III I. I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.85 40 1.96 30 2.19 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at:<50%F 2.83 25 at* 50%F 3.17 Figure A.60 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS and TBVOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision I Reload Safety Analysis for 105% OLTP Page A-62 4.0 0 FWCF o LRNB 3.5 A CRWE 3.0
,-E 2.5 0
0 0 2.0 00 A 0 A
1.5 6A I
I 6 I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.87 40 2.03 30 2.27 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at* 50%F 2.82 25 at <50%F 3.20 Figure A.61 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS and TBVOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-63 4.0 o FWCF o LRNB 3.5 A CRWE 3.0
=1-E nj 2.5 0
2.0 00 oo 0
1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.54 90 1.61 50 ---
50 1.90 40 2.04 30 2.27 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at < 50%F 2.95 25 at < 50%F 3.35 Figure A.62 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS and TBVOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-64 3.5 o FWCF o LRNB 3.0 A CRWE 2.5 41 C-, 0 0
2.0 0 0
0o Q0 A 0 1.5 ý III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.56 90 1.62 50 ---
50 1.85 40 1.98 30 2.21 30 at > 50%F 3.01 25 at > 50%F 3.35 30 atS 50%F 2.71 25 at* 50%F 3.04 Figure A.63 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS and TBVOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-65 3.5 O3 FWCF o LRNB 3.0 & CRWE 2.5 41 C) 0 0
2.0 02 0
0A A 0 1.5 0 0 0 III I I I I I I I 1.0 0 10 20 30 40 50 60 .70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.55 90 1.61 50 50 1.85 40 1.97 30 2.20 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at < 50%F 2.83 25 at* 50%F 3.17 Figure A.64 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS and TBVOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-66 3.5 0 FWCF 0 LRNB 3.0 a CRWE 2.5 0- 0 2.0 0 0 00 1.5 0 0 (
IIII I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.56 90 1.62 50 ---
50 1.87 40 1.98 30 2.21 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at* 50%F 2.7i
.25 at* 50%F 3.04 Figure A.65 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS and TBVOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-67 3.5 IIIIIII 3 FWCF o LRNB 3.0 F- A CRWE 2.5 I-E
-j 0~
0~ 0 0 0 2.0 l-0 o A0 1.5 o 6 III I I I I I II 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.55 90 1.61 50 ---
.50 1.85 40 1.97 30 2.20 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at < 50%F 2.83 25 at* 50%F 3.17 Figure A.66 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS and TBVOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-68 4.0 3.5 3.0 E
2.5 CL 2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.59 90 1.64 50 ---
50 1.89 40 2.05 30 2.29 30at > 50%F 3.13 25 at > 50%F 3.47 30 at < 50%F 2.82 25 at < 50%F 3.20 Figure A.67 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS and TBVOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-69 4.0 o3 FWCF o LRNB 3.5 ACRWE 3.0 Ej 2.5 0
0 0 2.0 0 A
1.5 I I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.57 90 1.63 50 ---
50 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at5<50%F 2.95 25 at* 50%F 3.35 Figure A.68 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS and TBVOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-70 3.5 0 FWCF o LRNB 3.0 A CRWE 4E 2.5 0
2.0 0 0 0 0 1.5 1- 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.59 50 ---
50 1.84 40 2.00 30 2.24 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at < 50%F 2.62 25 at* 50%F 2.84 Figure A.69 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-71 3.5 IIIII
- I I O3 FWCF o LRNB 3.0
- CRWE 2.5 0-0 2.0 0
1.5 k 0 0]
III!I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.51 90 1.58 50 ---
50 1.87 40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at < 50%F 2.75 25 at* 50%F 2.96 Figure A.70 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-72 3.5 o] FWCF o LRNB 3.0 1 A CRWE 2.5 E
-j 0L 0y 0 n
2.0' 0 A
0 o0 1.5 I~~~ 6 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.59 50 ---
50 1.86 40 2.00 30 2.24 30 at > 50%F 2.67 25 at> 50%F 2.90 30 at5<50%F 2.62 25 at < 50%F 2.84 Figure A.71 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision I Reload Safety Analysis for 105% OLTP Page A-73 3.5 o FWCF o LRNB A CRWE 3.0 1-2.5 I-ryQ-2.0 0 00 1.5 A 0 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.51 90 1.58 50 ---
50 1.87 40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at 5 50%F 2.75 25 at5<50%F 2.96 Figure A.72 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-74 3.5 o FWCF o LRNB 3.0 A CRWE 2.5 Q-0y 0
0 2.0 0 1.5 P 0 0 0 A 0 l~~ 6 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.56 90 1.61 50 ---
50 1.86 40 2.01 30 2.25 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at:<50%F 2.62 25 at < 50%F 2.84 Figure A.73 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-75 3.5 0 FWCF o LRNB 3.0 CRWE 2.5 Q-2r 0
2.0 0 0 00 AA 0 A 0
1.5 F-IIII I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.54 90 1.60 50 ---
50 1.89 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at < 50%F 2.75 25 at < 50%F 2.96 Figure A.74 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-76 3.5 o FWCF o LRNB 3.0 a CRWE E 2.5 2-.
0 2.0 00 00 o oio 0 0 1.5 1-1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.56 90 1.61 50 ---
50 1.87 40 2.01 30 2.25 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at5<50%F 2.62 25 at 5 50%F 2.84 Figure A.75 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-77 3.5 3.0 2.5
°--
l._
2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.60 50 ---
50 1.89 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at < 50%F 2.75 25 at:<50%F 2.96 Figure A.76 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-78 3.0 0] FWCF
- LRNB
- CRWE 2.5 F
-j 0
2.0 F 0- 00 A 03 1.5 1 0 I~~ 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.49 90 1.55 50 ---
50 1.89 40 1.92 30 2.15 30 at > 50%F 2.56 25 at > 50%F 2.77 30 at < 50%F 2.53 25 at:<50%F 2.72 Figure A.77 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-79 3.0 o FWCF o LRNB A CRWE 2.5 1
.J 0
o 2.0 0
0~
03 1.5 1 0 6 1.0 0 10 20 .30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.49 90 1.55 50 ---
50 1.87 40 1.92 30 2.15 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at5<50%F 2.65 25 at5<50%F 2.83 Figure A.78 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-80 3.0 o3 FWCF o LRNB
- CRWE 2.5 1-E 0
-j C. 2.0 [_ 0 0Y 0
1.5 l-i i3i 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.49 90 1.55 50 ---
50 1.91 40 1.92 30 2.15 30 at > 50%F 2.56 25 at > 50%F -2.77 30 at* 50%F 2.53 25 at5<50%F 2.72 Figure A.79 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-81 3.0 0 FWCF o LRNB A CRWE 2.5 ý-
0 2.0 1-0 C-,
1.5 I-I I I I I0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.49 90 1.55 50 ---
50 1.91 40 1.92 30 2.15 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at:<50%F 2.65 25 at < 50%F 2.83 Figure A.80 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-82 3.5 O FWCF o LRNB 3.0 A CRWE E 2.5 0
S2.0 0 00 00 A 103 10 1.5 0 A o 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(%of rated) Limit 100 1.52 90 1.59 50 ---
50 1.92 40 2.00 30 2.24 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at5<50%F 2.62 25 at <50%F 2.84 Figure A.81 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-83 3.5 IIIIIII I 0 FWCF o LRNB 3.0 A CRWE 2.5 E
0~
0~ 0 0
2.0 0 6 0.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.51 90 1.58 50 ---
50 1.91 40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at:<50%F 2.75 25 at < 50%F 2.96 Figure A.82 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-84 3.0 0 FWCF o LRNB A CRWE 2.5 I E
°_ 0 CL 2.0 0 of) 0~
A *-
0 1.5 I i i ii i I0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.53 90 1.58 50 ---
50 1.89 40 1.94 30 2.16 30 at > 50%F 2.56 25 at > 50%F 2.77 30 at < 50%F 2.53 25 at5<50%F 2.72 Figure A.83 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-85 3.0 I o3 FWCF o LRNB A CRWE 2.5 1-E
°--
0
. 2.0 0
Q3
- 2 1.5 I-I~E3I I 3I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.87 40 1.94 30 2.16 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at5<50%F 2.65 25 at* 50%F 2.83 Figure A.84 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-86 3.0 El FWCF 0 LRNB A. CRWE 2.5 H 0
2.0 0 00 CL) 103 10 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.53 90 1.58 50 ---
50 1.91 40 1.94 30 2.16 30 at > 50%F 2.56 25 at > 50%F 2.77 30 at < 50%F 2.53 25 at5<50%F 2.72 Figure A.85 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-87 3.0 o FWCF o LRNB A. CRWE 2.5 I-0 0
c) 2.0 0
x~
a.)
AA 6 6 1.5 1-1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.91 40 1.94
.30 2.16 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at5<50%F 2.65 25 at* 50%F 2.83 Figure A.86 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision I Reload Safety Analysis for 105% OLTP Page A-88 3.5 o FWCF o LRNB 3.0 1- A CRWE 2.5 I-a-
0 0
2.0 F- 0, 1.5 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.56 90 1.61 50 ---
50 1.92 40 2.01 30 2.25 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at5<50%F 2.62 25 at* 50%F 2.84 Figure A.87 BOG to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-89 3.5 0 FWCF o LRNB 3.0 A CRWE 2.5 41 Q-0y 0 0 0 2.0 o 6 6 A £ 1.5 III I I I I i I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.54 90 1.60 50 --
50 1.91 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at* 50%F 2.75 25 at < 50%F 2.96 Figure A.88 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP ,Page A-90 4.0 3.5 3.0 E
_ 2.5 2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.87 40 2.03 30 2.27 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at5<50%F 2.82 25 at < 50%F 3.20 Figure A.89 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times TBVOOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit I Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-91 4.0 O FWCF 3.5 o LRNB A CRWE 3.0 4-S2.5 a_
0 2.0 00 0
S A A 1.5 o 0 8 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.61 50 ---
50 1.90 40 2.04 30 2.27 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at < 50%F 2.95 25 at:<50%F 3.35 Figure A.90 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times TBVOOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-92 4.0 o FWCF o LRNB 3.5 A CRWE 3.0
-t CL 2.5 of a-0 2.0 0 A A 1.5 o 6 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.87 40 2.03 30 2.27 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at 5 50%F 2.82 25 at < 50%F 3.20 Figure A.91 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times TBVOOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-93 4.0 n FWCF o LRNB 3.5.
A CRWE 3.0 2.5 C-)
0 2.0 oo 1.5 1.0 i i i o 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.61 50 ---
50 1.90 40 2.04 30 2.27 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at* 50%F 2.95 25 at5<50%F 3.35 Figure A.92 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times TBVOOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-94 4.0 IIIIII II 0 FWCF o LRNB 3.5 A CRWE 3.0 E
CL 2.5
(,Y 0
2.0 0 0A 0A A0 1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.59 90 1.64 50 ---
50 1.89 40 2.05 30 2.29 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at5<50%F 2.82 25 atS 50%F 3.20 Figure A.93 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times TBVOOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP).
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-95 4.0 3.5 3.0 E
IJ CL 2.5 0y n
2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.57 90 1.63 50 ---
50 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at < 50%F 2.95 25 at < 50%F 3.35 Figure A.94 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times TBVOOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-96 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 E
a_ 2.5 a-)
0 2.0 0
°o A 03 1.5 A0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.59 90 1.64 50 ---
50 1.89 40 2.05 30 2.29 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at < 50%F 2.82 25 at5<50%F 3.20 Figure A.95 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times TBVOOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-97 4.0 n FWCF o LRNB 3.5 CRWE 3.0 7L, E~
0j 2.5 a) 0 0 2.0 oA A0 1.5 o 6 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.57 90 1.63 50 ---
50 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at* 50%F 2.95 25 at < 50%F 3.35 Figure A.96 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times TBVOOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-98 3.5
- FWCF o LRNB 3.0
- CRWE E 2.5 0
2.0 0 0 0 1.5 [
00 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.89 40 1.96 30 2.19 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at < 50%F 2.71 25 at < 50%F 3.04 Figure A.97 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times TBVOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit I Cycle 9 Revision I Reload Safety Analysis for 105% OLTP Page A-99 3.5 o FWCF o LRNB 3.0 a CRWE 2.5 E
C-0 2.0 0
0 1.5 II I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.87 40 1.96 30 2.19 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at < 50%F 2.83 25 at* 50%F 3.17 Figure A.98 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times TBVOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-100 3.5 I I I I I . I I I o FWCF o LRNB 3.0 CRWE 2.5 n
0~ 0 ME 2.0 0 A 8 0
A 0
1.5 1-III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.91 40 1.96 30 2.19 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at* 50%F 2.71 25 at < 50%F 3.04 Figure A.99 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times TBVOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-101 3.5
-n FWCF 0 LRNB 3.0 A CRWE 2.5 n~
0 2.0 0
A0 6 A 6 1.5 ý-
III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.91 40 1.96 30 2.19 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at* 50%F 2.83 25 at* 50%F 3.17 Figure A.100 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times TBVOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-102 4.0 IIII
- I
- FWCF o LRNB 3.5 A CRWE 3.0 E
._j 0_ 2.5 n,-
03 0
2.0 0 0 A AA 0 1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.92 40 2.03 30 2.27 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at < 50%F 2.82 25 at < 50%F 3.20 Figure A.101 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-1O Fuel NSS Insertion Times TBVOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-103 4.0 o FWCF o LRNB 3.5 A CRWE 3.0
-J 2.5 0-,
0 2.0 0 00 0
o 1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.61 50 ---
50 1.91 40 2.04 30 2.27 3at>500/.F 3.17 25 at > 50%F 3.47 30 at < 50%F 2.95 25 at* 50%F 3.35 Figure A.102 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times TBVOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A- 104 3.5 0 FWCF o LRNB 3.0 A CRWE 2.5 QE Of n~ 0 0
2.0 0 0
A 1.5 A Q g iii i i I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.56 90 1.62 50 ---
50 1.89 40 1.98 30 2.21 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at:< 50%F 2.71 25 at < 50%F 3.04 Figure A.103 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times TBVOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-105 3.5 o FWCF o LRNB 3.0 A CRWE 2.5 ry 0n 0
0 2.0 0 o 0
0 8 A0 1.5 II I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.87 40 1.97 30 2.20 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at < 50%F 2.83 25 at* 50%F 3.17 Figure A.104 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times TBVOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-106 3.5 O] FWCF o LRNB 3.0 A CRWE 2.5
_j a-) 0 0
2.0 0 0
00 A.
1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.56 90 1.62 50 ---
50 1.91 40 1.98 30 2.21 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at5<50%F 2.71 25 at5<50%F 3.04 Figure A.105 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times TBVOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-107 3.5 n FWCF o LRNB 3.0 A CRWE 2.5 CL 0
2.0 0 0 0 d
1.5 6 6 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.91 40 1.97 30 2.20 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at < 50%F 2.83 25 at - 50%F 3.17 Figure A.106 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times TBVOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-108 4.0 IIIII II in FWCF 0 LRNB 3.5 A CRWE 3.0
- t 2.5 C-)
0 2.0 0 0 I0 AA 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.59 90 1.64 50 ---
50 1.92 40 2.05 30 2.29 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at5<50%F 2.82 25 at:< 50%F 3.20 Figure A.107 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times TBVOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-109 4.0 0 FWCF o LRNB 3.5 a CRWE 3.0 EJ 2.5 n~
0 0
2.0 0
1.5 6 I6 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRn
(% of rated) Limit 100 1.57 90 1.63 50 ---
50 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at5<50%F 2.95 25 at5<50%F 3.35 Figure A.108 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times TBVOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-110 3.5 I I* II o3 FWCF o LRNB 3.0 A* CRWE 2.5 0~ 0
()
2.0 0 1.5 [-
S I I I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.59 50 ---
50 1.89 40 2.00 30 2.24 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at < 50%F 2.62 25 at5<50%F 2.84 Figure A.109 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times FHOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-111 3.5 o FWCF 0 LRNB 3.0 A CRWE E 2.5 ry 0- 0 2.0 0
1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.51 90 1.58 50 ---
50 1.87 40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at5<50%F 2.75 25 at < 50%F 2.96 Figure A.110 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times FHOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-1 12 3.5 a FWCF o LRNB 3.0 A CRWE 2.5 41 0
2.0 0 A 0 1.5 I I I II I I0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.59 50 ---
50 1.91 40 2.00 30 2.24 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at* 50%F 2.62 25 at5<50%F 2.84 Figure A.111 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times FHOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-i 13 3.5 o FWCF o LRNB 3.0 A CRWE 2.5 O
0~
0E 2.0 0
1.5 1-III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.51 90 1.58 50 ---
50 1.91 40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at:<50%F 2.75 25 at < 50%F 2.96 Figure A.112 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times FHOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-1 14 3.5 O] FWCF o LRNB 3.0 A CRWE 2.5 ft 0
0_
- 2.0 0 1.5 F A Q iii i i I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.56 90 1.61 50 ---
50 1.89 40 2.01 30 2.25 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at:< 50%F 2.62 25 at < 50%F 2.84 Figure A.113 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times FHOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-i 15 3.5 o FWCF o LRNB 3.0 a CRWE 2.5 O-0 2.0 0
1.5 -
III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.60 50 ---
50 1.89 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at < 50%F 2.75 25 at < 50%F 2.96 Figure A.114 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times FHOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-116 3.5 3.0 2.5 ry 0
2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.56 90 1.61 50 ---
50 1.91 40 2.01 30 2.25 30'at > 50%F 2.67 25 at > 50%F 2.90 30 at* 50%F 2.62 25 at < 50%F 2.84 Figure A.115 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times FHOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-117 3.5 0 FWCF 0 LRNB 3.0 k A CRWE 2.5 1-
-j 0~
0~ 0 0
2.0 F 0
0 0 1.5 - 6 A 6 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
. Power MCPRp
(% of rated) Limit 100 1.54 90 1.60 50 ---
50 1.91 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at:<50%F 2.75 25 at* 50%F 2.96 Figure A.116 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times FHOOS and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-118 4.0 3.5 3.0 E
-j 2.5 0-2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.87 40 2.03 30 2.27 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at5<50%F 2.82 25 at < 50%F 3.20 Figure A.117 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS, TBVOOS, and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-I 19 4.0 I I I I I I I 0 FWCF 0 LRNB 3.5 A CRWE 3.0
- t EJ 2.5 0
2.0 0
1.5 1.0 II I I . I I I I . I I 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.61 50 ---
50 1.90 40 2.04 30 2.27 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at:<50%F 2.95 25 at* 50%F 3.35 Figure A.118 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS, TBVOOS, and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-120 4.0 o FWCF o LRNB 3.5 a CRWE 3.0 E
_j o_ 2.5 0Y 0
2.0 0 .
1.5 A6 III I I I g I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.87 40 2.03 30 2.27 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at* 50%F 2.82 25 at < 50%F 3.20 Figure A.119 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS, TBVOOS, and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-121 4.0 0 FWCF o LRNB 3.5 a CRWE 3.0 7t 2.5 a-0 2.0 0 AA A 1.5 e III I I I I I I I 1.0 0 10 20 30 4-0 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.54 90 1.61 50 ---
50 1.90 40 2.04 30 2.27 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at5<50%F 2.95 25 at* 50%F 3.35 Figure A.120 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS, TBVOOS, and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-122 4.0 3.5 3.0 E
ry 2.5 n~
2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.59 90 1.64 50 ---
50 1.89 40 2.05 30 2.29 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at5<50%F 2.82 25 at<5 50%F 3.20 Figure A.121 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-123 4.0 3 FWCF 3.5 o LRNB A CRWE 3.0 E
2.5 0y 0n 0
2.0 0 A
1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.57 90 1.63 50 ---
50 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at* 50%F 2.95 25 at* 50%F 3.35 Figure A.122 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-124 4.0 o FWCF o LRNB 3.5 A CRWE E
nJ 3.0 2.5 3
0 2.0 0 0 0 AA 1.5 0 0 i i i ii i iA 1.0 i i i i i i 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.59 90 1.64 50 ---
50 1.89 40 2.05 30 2.29 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at* 50%F 2.82 25 at < 50%F 3.20 Figure A.123 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-125 4.0 O FWCF o LRNB 3.5 A CRWE 3.0
__j 2.5 01.
0ý 0
2.0 A
0 1.5 oI I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.57 90 1.63 50 ---
50 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at* 50%F 2.95 25 at < 50%F 3.35 Figure A.124 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-126 3.5 3.0 E 2.5 2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.89 40 1.96 30 2.19 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at < 50%F 2.71 25 at5<50%F 3.04 Figure A.125 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS, TBVOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-127 3.5 o FWCF o LRNB 3.0 A CRWE
.E 2.5
-j 0- 0 2.0 0
A A 0 1.5 III I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.87 40 1.96 30 2.19 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at* 50%F 2.83 25 at* 50%F 3.17 Figure A.126 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS, TBVOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-128 3.5 3.0 2.5 CL ci.
a_
2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.91 40 1.96 30 2.19 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at5<50%F 2.71 25 at!<50%F 3.04 Figure A.127 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS, TBVOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-129 3.5 o1 FWCF o LRNB 3.0 A CRWE 2.5 OJ LrY n
2.0 A 0 1.5 6 o IIIII I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.58 50 ---
50 1.91 40 1.96 30 2.19 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at:<50%F 2.83 25 at* 50%F 3.17 Figure A.128 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS, TBVOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-130 4.0 o FWCF o LRNB 3.5 A CRWE 3.0
- t 2.5 c-,
0 0 0 2.0 00 "0
0 0
1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.92 40 2.03 30 2.27 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at5<50%F 2.82 25 at* 50%F 3.20 Figure A.129 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS, TBVOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-131 4.0 11 FWCF
- LRNB 3.5 A CRWE 3.0 7t E~
2.5 0*
2.0 0 00 AA 1.5 6 III I I I I i I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 10O0 1.54 90 1.61 50 ---
50 1.91 40 2.04 30 2.27 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at* 50%F 2.95 25 at 5 50%F 3.35 Figure A.130 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS, TBVOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A- 132 3.5 EO FWCF o LRNB
,3.0 A CRWE E 2.5
_j 0
0
, 2.0 0 0
El f)
ýýýO A 1.5 1-1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.56 90 1.62 50 ---
50 1.89 40 1.98 30 2.21 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at* 50%F 2.71 25 at5<50%F 3.04 Figure A.131 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-l Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-133 3.5 3.0
- 2.5 OJ 0_
C-)
2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 50 1.87 40 1.97 30 2.20 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at5<50%F 2.83 25 at5<50%F 3.17 Figure A.132 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-134 3.5
- LRNB 3.0
- CRWE 41 2.5 3 0~ 0 0
12 2.0 0 0
0 A 9 1.5 [
III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100, 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.56 90 1.62 50 ---
50 1.91 40 1.98 30 2.21 30 at > 50%F 3.01 25 at > 50%F 3.35 30 at < 50%F 2.71 25 at* 50%F 3.04 Figure A.133 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A- 135 3.5
- FWCF o LRNB 3.0
- CRWE E 2.5 o-0-
0 02 0
- 22.0 00 A
0 A6 1.5 [ S A 6~6 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.91 40 1.97 30 2.20 30 at > 50%F 3.03 25 at > 50%F 3.35 30 at < 50%F 2.83 25 at* 50%F 3.17 Figure A.134 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-136 4.0
[] FWCF o LRNB 3.5
- CRWE 3.0 a- 2.5 0
0 0 2.0 0 1.5 A Q III I a I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.59 90 1.64 50 ---
50 1.92 40 2.05 30 2.29 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at5<50%F 2.82 25 at < 50%F 3.20 Figure A.135 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for ATRIUM-1O Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-137 4.0 o FWCF o LRNB 3.5 a CRWE 3.0 E
-_J c_ 2.5 n--
0 2.0 0 0 0 A
1.5 6 I6 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.57 90 1.63 50--
50 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at:<50%F 2.95 25 at:<50%F 3.35 Figure A.136 BOC to FFTR/Coastdown Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-138 3.5 3.0 2.5 CL) 2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.59 50 ---
50 1.89 40 2.00 30 2.24 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at:<50%F 2.62 25 at5<50%F 2.84 Figure A.137 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-139 3.5 3.0 2.5 a-2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.51 90 1.58 50 ---
50 1.87 40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at* 50%F 2.75 25 at:<50%F 2.96 Figure A.138 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-140 3.5
- FWCF o LRNB 3.0
- CRWE 2.5 41 0
2.0 0 0
0 0 0
A0 A0 1.5 0
1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.52 90 1.59 50 ---
50 1.91 40 2.00 30 2.24 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at5<50%F 2.62 25 at5<50%F 2.84 Figure A.139 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-141 3.5
- FWCF o LRNB 3.0 A CRWE 4E 2.5
-j 0y 0
2.0 00 1.5 1-I I I II I0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.51 90 1.58 50 ---
50 1.91 40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at5<50%F 2.75 25 at < 50%F 2.96 Figure A.140 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-142 3.5 I III o FWCF o LRNB 3.0 CRWE 2.5 41 0
0 2.0 0 0 1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.56 90 1.61 50 ---
50 1.89 40, 2.01 30 2.25 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at* 50%F 2.62 25 at < 50%F 2.84 Figure A.141 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-143 3.5 0 FWCF o LRNB 3.0 A CRWE 2.5
-j 0L 0f a- 0 2.0 0 0
1.5 1 IiI I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.60 50 50 1.89 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at5<50%F 2.75 25 at < 50%F 2.96 Figure A.142 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-144 3.5 I I I I I I o FWCF o LRNB 3.0 A CRWE 2.5 0
0~
2.0 0 000 I I 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.56 90 1.61 50 ---
50 1.91 40 2.01 30 2.25 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at5<50%F 2.62 25 at< 50%F 2.84 Figure A.143 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit I Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-145 3.5 0 FWCF o LRNB 3.0 A CRWE 2.5
-J 0~
rat:
0 C) 0 0 2.0 0 6 A 66 1.5 1.0 III I I I I I -I I 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.60 50 ---
50 1.91 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at5<50%F 2.75 25 at < 50%F 2.96 Figure A.144 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-146 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 E
-j 2.5 o-,
0 2.0 0 o
A0 1.5 A 0 o III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.89 40 2.03 30 2.27 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at < 50%F 2.82 25 at 5 50%F 3.20 Figure A.145 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-147 4.0 O FWCF o LRNB 3.5 A CRWE 3.0 2.5 0
0 2.0 00 1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.61 50 ---
50 1.90 40 2.04 30 2.27 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at5<50%F 2.95 25 at 5 50%F 3.35 Figure A.146 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-148 4.0 0 FWCF o LRNB 3.5 A CRWE 3.0
-j 2.5 CL, 0
2.0 0 A 0 0 A
1.5 1.0 III I I I I I I I 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.91 40 2.03 30 2.27 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at < 50%F 2.82 25 at 5 50%F 3.20 Figure A.147 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-149 4.0 3.5 3.0
- t 2.5 0-2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.61 50 ---
50 1.91 40 2.04 30 2.27 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at5<50%F 2.95 25 at < 50%F 3.35 Figure A.148 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit I Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-150 4.0 0 FWCF o LRNB 3.5 A CRWE 3.0 0t~
E~ 2.5 C-)
0 2.0 0 A
1.5 A Q III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.59 90 1.64 50 ---
50 1.89 40 2.05 30 2.29 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at* 50%F 2.82 25 at5<50%F 3.20 Figure A.149 BOC to NEOC Power-Dependent MCPR Limits for
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision I Reload Safety Analysis for 105% OLTP Page A-151 4.0 0 FWCF 3.5 o LRNB A CRWE 3.0 E
o_ 2.5 0
2.0 0
1.5 6
1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.57 90 1.63 50 ---
50 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at5<50%F 2.95 25 at* 50%F 3.35 Figure A.150 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A- 152 4.0 n FWCF o LRNB 3.5 A CRWE 3.0
-t E~
2.5 n~
0 2.0 0 A A0 A
1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.59 90 1.64 50 -7 50 1.91 40 2.05 30 2.29 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at* 50%F 2.82 25 at < 50%F 3.20 Figure A.151 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-153 4.0 IIIIIII I O3 FWCF o LRNB 3.5 A CRWE 3.0 E
°_
_ 2.5
,-)
0 2.0 0 1.5 0 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.57 90 1.63 50 ---
50 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at < 50%F 2.95 25 at < 50%F 3.35 Figure A.152 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision I Reload Safety Analysis for 105% OLTP Page A-154 4.0 3.5 3.0 2.5 0~
2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.89 40 2.03 30 2.27 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at5<50%F 2.82 25 at < 50%F 3.20 Figure A.153 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-155 4.0 0 FWCF o LRNB 3.5 A CRWE 3.0 E
2.5 2.0 0 1.5 I I I I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.54 90 1.61 50 ---
50 1.90 40 2.04 30 2.27 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at <50%F 2.95 25 at* 50%F 3.35 Figure A.154 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-156 4.0 3.5 3.0 Ej 2.5 n-2.0 1.5 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.55 90 1.61 50 ---
50 1.91 40 2.03 30 2.27 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at < 50%F 2.82 25 at* 50%F 3.20 Figure A.155 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel, NSS Insertion Times EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1, Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-157 4.0 o FWCF o LRNB 3.5 A CRWE 3.0
,-E
-J CL 2.5 0
0 2.0 o
00 0
1.5 A 6 A 6 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRn
(% of rated) Limit 100 1.54 90 1.61 50 ---
50 1.91 40 2.04 30 2.27 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at5<50%F 2.95 25 at* 50%F 3.35 Figure A.156 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-158 4.0 o3 FWCF o LRNB 3.5 A CRWE 3.0 E
2.5 0n 0
2.0 0 o0o 0A 1.5 II I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRp
(% of rated) Limit 100 1.59 90 1.64 50 ---
50 1.89 40 2.05 30 2.29 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at* 50%F 2.82 25 at < 50%F 3.20 Figure A.157 BOC to NEOC Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-159 4.0 IIIIII I 0 FWCF o LRNB 3.5 A CRWE 3.0 E
. 2.5 a-)
0 2.0 0
1.5 66 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.57 90 1.63 50 ---
50 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 25 at > 50%F 3.47 30 at5<50%F 2.95 25 at* 50%F 3.35 Figure A.158 BOC to NEOC Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A- 160 4.0
- FWCF o LRNB 3.5
- CRWE 3.0
-j 2.5 0ý C) 0 2.0 0 0
1.5 III I I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated) 9 Power MCPRp
(% of rated) Limit 100 1.59 90 1.64 50 ---
50 1.91 40 2.05 30 2.29 30 at > 50%F 3.13 25 at > 50%F 3.47 30 at < 50%F 2.82 25 at < 50%F 3.20 Figure A.159 BOC to EOCLB Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-161 4.0 o FWCF o LRNB 3.5
- CRWE 3.0 E
_j a~ 2.5 0y n-0 2.0 0 1.5 o o 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power MCPRP
(% of rated) Limit 100 1.57 90 1.63 50 ---
50 1.92 40 2.05 30, 2.29 30 at > 50%F 3.17 25 at > 50%F 3.47 30 atS 50%F 2.95 25 at 5 50%F 3.35 Figure A.160 BOC to EOCLB Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-162 1.4 I I I o FWCF o LRNB 1.2 1.0
-j 0-00 CD .8 o0 0 a 0q
.6 i ii ii i0
.4 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power LHGRFACp
(% of rated) Multiplier 100 1.00 30 0.64 30 at > 50%F 0.47 25 at > 50%F 0.47 30 at < 50%F 0.47 25 at < 50%F 0.47 Figure A.161 All Exposures Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel NSS/TSSS Insertion Times EOOS with TBV In-Service AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-163 1.5 I I I I 0 Required LHGRA 1.25 I II I I 1.0 0 E
°_
Q_1
.75 L-b_
.5 7
.25
.0 III I I I I I I I 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power LHGRFACp
(% of rated) Multiplier 100 1.00 75 0.78 30 0.60 30 at > 50%F 0.44 25 at > 50%F 0.42 30 at* 50%F 0.44 25 at < 50%F 0.44 Figure A.162 All Exposures Power-Dependent LHGR Multipliers for GE14 Fuel NSS/TSSS Insertion Times EOOS with TBV In-Service AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety\Analysis for 105% OLTP Page A-164 1.5 1.25 1.0 E
.75 0
r Ij
.5
.25
.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power LHGRFACP
(%of rated) Multiplier 100 0.90 90 0.83 30 0.62 30 at > 50%F 0.43 25 at > 50%F 0.39 30 at5<50%F 0.47 25 at* 50%F 0.46 Figure A.163 All Exposures Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel NSS/TSSS Insertion Times EOOS with TBVOOS AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 1 Reload Safety Analysis for 105% OLTP Page A-165 1.5 II I I I I I I[ Required LHGRFAC 1.25 1.0 0
.J 0*
.75 L-
-r r-
.5
.25
.0 I I I I I I I I I I 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Power LHGRFACp
(% of rated) Multiplier 100 0.99 75 0.77 30 0.58 30 at > 50%F 0.37 25 at > 50%F 0.31 30 at:<50%F 0.44 25 at < 50%F 0.43 Figure A.164 All Exposures Power-Dependent LHGR Multipliers for GE14 Fuel NSS/TSSS Insertion Times EOOS with TBVOOS AREVA NP Inc.