ML13070A314

ANP-3167(NP), Revision 0, Browns Ferry Unit 2 Cycle 19 Reload Analysis

ML13070A314
Person / Time
Site:	Browns Ferry
Issue date:	11/30/2012
From:	AREVA NP
To:	Office of Nuclear Reactor Regulation
References
ANP-3167(NP), Rev 0
Download: ML13070A314 (174)

Text

ATTACHMENT 13 Browns Ferry Nuclear Plant (BFN)

Units 1, 2, and 3 Technical Specifications (TS) Change 478 Addition of Analytical Methodologies to Technical Specification 5.6.5.b for Browns Ferry 1, 2, & 3, and Revision of Technical Specification 2.1.1.2 for Browns Ferry Unit 2, in Support of ATRIUM-10 XM Fuel Use at Browns Ferry Reload Safety Analysis Report Attached is the non proprietary version of the Reload Safety Analysis Report.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis November 2012 A

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis sja

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Revision 0 Copyright © 2012 AREVA NP Inc.

All Rights Reserved

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page i Nature of Changes Item Page Description and Justification

1. All This is the initial release.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis 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 Hydrodynamic Stability ................................... 4-2 5.0 Anticipated O perational O ccurrences ........................................................................... 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 TBVO O S ............................................................................................. 5-7 5.3.2 FHO O S ............................................................................................... 5-8 5.3.3 PLUOO S ............................................................................................. 5-8 5.3.4 Com bined TBVO O S and FHOO S ....................................................... 5-8 5.3.5 Com bined TBVOO S and PLUO O S ..................................................... 5-9 5.3.6 Com bined FHOO S and PLUO O S ....................................................... 5-9 5.3.7 Combined TBVOOS, FHOOS, and PLUOOS ...................................... 5-9 5.3.8 Single-Loop O peration ........................................................................ 5-9 5.4 Licensing Power Shape .................................................................................. 5-10 6.0 Postulated Accidents ....................................................... ............................................ 6-1

.6.1 Loss-of-Coolant-Accident (LO CA) ..................................................................... 6-1 6.2 Control Rod Drop Accident (CRDA) .................................................................. 6-1 6.3 Fuel and Equipm ent Handling Accident ........................................................... 6-2 6.4 Fuel Loading Error (Infrequent Event) ............................................................... 6-2 6.4.1 Mislocated Fuel Bundle ....................................................................... 6-2 6.4.2 Misoriented Fuel Bundle ..................................................................... 6-3 7.0 Special Analyses .......................................................................................................... 7-1 7.1 ASM E Overpressurization Analysis ................................................................... 7-1 7.2 ATW S Event Evaluation .................................................................................... 7-2 7.2.1 ATW S Overpressurization Analysis ..................................................... 7-2 7.2.2 Long-Term Evaluation ......................................................................... 7-3 7.3 Standby Liquid Control System ......................................................................... 7-3 7.4 Fuel Criticality ................................................................................................... 7-4 8.0 O perating Lim its and CO LR Input ................................................................................. 8-1 8.1 MCPR Lim its ..................................................................................................... 8-1 8.2 LHG R Lim its ..................................................................................................... 8-1 AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page iii 8.3 MAP 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 ATRIUM 1OXM Fuel Introduction at B row ns F e rry .................................................................................................................. 2 -3 2.2 Disposition of Operating Flexibility and EOOS Options on Limiting Events ................. 2-11 2.3 Methodology and Evaluation Models for Cycle Specific Reload Analyses ................... 2-12 4.1 Fuel- and Plant-Related Uncertainties for Safety Limit MCPR Analyses ....................... 4-3 4.2 Results Summary for Safety Limit MCPR Analyses ....................................................... 4-4 4 .3 O P R M S etpoints ............................................................................................................ 4-5 4.4 BSP Endpoints for Browns Ferry Unit 2 Cycle 19 .......................................................... 4-6 5.1 Exposure Basis for Transient Analysis ......................................................................... 5-11 5.2 Scram Speed Insertion Times ..................................................................................... 5-12 5.3 Base Case LRNB Transient Results ............................................................................ 5-13 5.4 Base Case TTNB Transient Results ............................................................................ 5-14 5.5 Base Case FWCF Transient Results ........................................................................... 5-15 5.6 Loss of Feedwater Heating Transient Analysis Results .............................................. 5-16 5.7 Control Rod Withdrawal Error ACPR Results ............................................................... 5-16 5.8 RBM Operability Requirements .................................................................................... 5-17 5.9 Flow-Dependent MCPR Results ..................................... 5-17 5.10 Licensing Basis Core Average Axial Power Profile ..................................................... 5-18 7.1 ASME Overpressurization Analysis Results ................................................................... 7-5 7.2 ATWS Overpressurization Analysis Results .................................................................. 7-6 7.3 [] .................. 7-7 8.1 MCPRP Limits for NSS Insertion Times .......................................................................... 8-3 8.2 MCPRp Limits for TSSS Insertion Times ........................................................................ 8-5 8.3 Flow-Dependent MCPR Limits ATRIUM 1OXM and ATRIUM-10 Fuel ........................... 8-7 8.4 Steady-State LHGR Limits ............................................................................................. 8-7 8.5 LH G R FAC P Multipliers ................................................................................................... 8-8 8 .6 LH G R FAC f Multipliers .................................................................................................... 8-9 8 .7 MA P LH G R Lim its ........................................................................................................... 8-9 AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page iv Figures 1.1 Browns Ferry Power/Flow Map - 105% OLTP .............................................................. 1-3 5.1 EOCLB LRNB at 1OOP/105F - TSSS Key Parameters ............................................... 5-19 5.2 EOCLB LRNB at 1OOP/1 05F - TSSS Sensed Water Level ......................................... 5-20 5.3 EOCLB LRNB at looP/1 05F - TSSS Vessel Pressures ............................................. 5-21 5.4 EOCLB FWCF at looP/1 05F - TSSS Key Parameters .............................................. 5-22 5.5 EOCLB FWCF at 1 GOP/1 05F - TSSS Sensed Water Level ........................................ 5-23 5.6 EOCLB FWCF at 1 GOP/1 05F - TSSS Vessel Pressures ........................................... 5-24 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 v e l ............................................................................................................................ 7-9 7.3 MSIV Closure Overpressurization Event at 102P/105F - Vessel P ressu re s ................................................................................................................... 7-10 7.4 MSIV Closure Overpressurization Event at 102P/105F - Safety/Relief Valve Flow R ates ....................................................................................................... 7-11 7.5 PRFO ATWS Overpressurization Event at 1OOP/81F - Key Parameters .................... 7-12 7.6 PRFO ATWS Overpressurization Event at 1OOP/81F - Sensed Water

.Le v e l .......................................................................................................................... 7 -1 3 7.7 PRFO ATWS Overpressurization Event at 1OOP/81F - Vessel Pressures .................. 7-14 7.8 PRFO ATWS Overpressurization Event at 1OOP/81 F - Safety/Relief Va lve F low Rates ....................................................................................................... 7-15 AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page v 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 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 EOOS 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 AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page vi 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 below which direct scram on TSVITCV 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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page vii 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 TBVIS turbine bypass valves in-service TBVOOS turbine bypass valves out-of-service 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 ACPR change in critical power ratio AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 1-1 1.0 Introduction Reload licensing analyses results generated by AREVA NP Inc. (AREVA) 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 1OXM*

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assemblies and 492 irradiated ATRIUM-10 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.

• ATRIUM is a trademark of AREVA NP.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis 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 temperature reduction (FFTR) /

coastdown Equipment Out-of-Service (EOOS) Conditions*

Turbine bypass valves out-of-service (TBVOOS)

Feedwater heaters out-of-service (FHOOS)

Power load unbalance out-of-service (PLUOOS)

Combined TBVOOS and FHOOS Combined TBVOOS and PLUOOS Combined FHOOS and PLUOOS Combined 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, EOC-RPT-OOS, 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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 1-3 140 130 120 110 100

' 90 e

• 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

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 2-1 2.0 Disposition of Events The objective of the disposition of events is to identify the limiting events which must be analyzed to support operation at the Browns Ferry Nuclear Power Station with the introduction of ATRIUM 1OXM 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.

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.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 2-2 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:

• FSAR analysis

• 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 is 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 2 and 3).

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 2-3 Table 2.1 Disposition of Events Summary for ATRIUM 1OXM Fuel Introduction at Browns Ferry FSAR Section Event /Analysis Disposition Status Comments 3.2 Fuel mechanical Address initial reload Cycle specific analysis (results and design analyses generally do not change from cycle-to-cycle, unless a design feature is modified).

Refer to Reference 4 for the analysis, acceptance criteria, methodology and evaluation model.

Demonstrate design criteria are met.

3.6 Nuclear design Address each reload Cycle specific analysis.

Refer to Reference 1 for the analysis, acceptance criteria, methodology and evaluation model.

Demonstrate design criteria are met.

3.7 Thermal and Address each reload Plant specific and cycle specific analysis.

hydraulic design Demonstrate design criteria are met. Fuel hydraulic design and compatibility results are provided in Reference 5. Refer to Reference 5 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 each reload Cycle specific analysis.

control system Analysis performed each reload to verify adequate SLCS shutdown capacity.

4.2 Reactor vessel and No further analyses FSAR analysis.

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 1OXM fuel is sufficiently similar to the spectrum applied in the licensing basis evaluation of the vessel irradiation limits. The introduction of ATRIUM 1OXM fuel will have an insignificant effect on the fluence (E > 1.0 MeV) at the reactor vessel wall and internals.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 2-4 Table 2.1 Disposition of Events Summary for ATRIUM 1OXM Fuel Introduction at Browns Ferry (Continued)

FSAR Section Event /Analysis Disposition Status Comments 4.4 Nuclear system Address each reload Cycle specific analysis (overpresurization),

pressure relief plant specific analysis (LOCA).

system 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 6 and 7).

5.2 Primary No further analyses FSAR analysis.

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 previous AREVA fuel. The evaluation is applicable for the introduction of ATRIUM 1OXM fuel.

5.3 Secondary No further analyses FSAR analysis.

Containment required System The secondary containment basis is independent of fuel design.

6.0 Emergency core Address each reload Plant specific analysis and cycle specific cooling systems analysis.

LOCA is a potentially limiting accident.

Limiting break characteristics are identified for the initial ATRIUM 1OXM reload. Refer to References 6 and 7 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 each reload Plant specific and cycle specific analysis.

monitoring system Cycle specific OPRM trip setpoint calculations. RBM setpoints evaluated for the CRWE event. Backup stability protection.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 2-5 Table 2.1 Disposition of Events Summary for ATRIUM 1OXM Fuel Introduction at Browns Ferry (Continued)

FSAR Section Event /Analysis Disposition Status Comments 7.19 Anticipated Address each reload Cycle specific analysis.

transient without 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 1OXM (Section 7.2.2).

8.10 Station blackout No further analyses FSAR analysis.

required The licensing basis analysis remains applicable. ATRIUM 1OXM fuel is designed to perform in a manner similar to and analogous with fuel of current and previous designs.

10.2 New fuel storage Not applicable for ATRIUM 10XM will not be stored in the ATRIUM 1OXM new fuel storage vault.

10.3 Spent fuel storage Address each reload Plant specific analysis.

Refer to References 9 and 35 for the analysis, acceptance criteria, methodology, and evaluation model.

Evaluated for spent fuel storage racks.

Confirm applicability each reload.

10.11 Fire protection Address initial reload Plant specific analysis.

systems This issue is addressed in Reference 10.

14.5.2.1 Generator trip No further analyses FSAR analysis.

(TCV fast closure) required Bound by the generator trip with turbine bypass valve failure.

14.5.2.2 Generator trip Address each reload Cycle specific analysis.

(TCV fast closure) with turbine This event is a potentially limiting AOT.

bypass valve failure 14.5.2.2.4 LRNB with EOC- Address each reload Cycle specific analysis.

RPT-OOS This event is a potentially limiting AOT.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 2-6 Table 2.1 Disposition of Events Summary for ATRIUM 1OXM Fuel Introduction at Browns Ferry (Continued)

FSAR Section Event /Analysis Disposition Status Comments 14.5.2.3 Loss of condenser No further analyses FSAR analysis.

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 initial reload Cycle specific analysis, for initial reload.

valves failure following turbine Generally bound by the generator trip with trip (TTNB), high turbine bypass valve failure.

power 14.5.2.6 Turbine bypass Address initial reload Cycle specific analysis, for initial reload.

valves failure 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.

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.

failure (downscale) required Eliminated as an AOT by the installation of a digital fault-tolerant main turbine electro-hydraulic control system.

14.5.3.1 Loss of feedwater Address each reload Cycle specific analysis.

heater (LFWH)

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.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 2-7 Table 2.1 Disposition of Events Summary for ATRIUM 1OXM Fuel Introduction at Browns Ferry (Continued)

FSAR Section Event /Analysis Disposition Status Comments 14.5.3.3 Inadvertent HPCI No further analysis FSAR analysis.

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 each reload Cycle specific analysis.

withdrawal during 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 each reload Cycle specific analysis.

misoriented fuel assembly 14.5.5.1 Pressure regulator Address each reload FSAR analysis and cycle specific analysis.

failure open (PRFO) 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.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 2-8 Table 2.1 Disposition of Events Summary for ATRIUM 1OXM Fuel Introduction at Browns Ferry (Continued)

FSAR Section Event /Analysis Disposition Status Comments 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.

14.5.7.1 Recirculation flow Address each reload Cycle specific analysis.

control failure -

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 each reload Cycle specific analysis.

controller failure (FWCF) - This event is a potentially limiting AOT.

maximum demand AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 2-9 Table 2.1 Disposition of Events Summary for ATRIUM 1OXM Fuel Introduction at Browns Ferry (Continued)

FSAR Section Event /Analysis Disposition Status Comments 14.5.8.2 Feedwater Address each reload Cycle specific analysis.

controller failure (FWCF) - This event is a potentially limiting AOT.

maximum demand with EOC-RPT-OOS 14.5.8.3 Feedwater Address each reload Cycle specific analysis.

controller failure (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 each reload Cycle specific analysis.

accident (CRDA)

Consequences of the CRDA are evaluated to confirm that the acceptance criteria are satisfied.

14.6.3 Loss-of-coolant Address each reload Plant specific analysis and cycle specific accident (LOCA) analysis.

Consequences of the LOCA are evaluated to determine appropriate cycle-specific MAPLHGR limits. Refer to References 6 and 7 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 each reload Plant specific analysis.

Refer to Reference 11 for the analysis, acceptance criteria, methodology, and evaluation model.

Consequences of the refueling accident are evaluated to confirm that the acceptance criteria are satisfied.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 2-10 Table 2.1 Disposition of Events Summary for ATRIUM 1OXM Fuel Introduction at Browns Ferry (Continued)

FSAR Section Event /Analysis Disposition Status Comments 14.6.5 Main steam line No further analysis FSAR analysis.

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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 2-11 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) 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) each of these events/analyses.

LRNB 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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 2-12 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 2 SAFLIM3D 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 15 RODEX2 LHGR operating limits established to meet the fuel 16 RODEX4 failure criteria.

3.8 Standby liquid 17 CASMO-4 SLCS criteria: Shutdown margin control system /MICROBURN- of at least 0.88% Ak/k.

B2 4.4 Nuclear system 2 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 18 HUXY LOCA criteria: 10 CFR 50.46.

cooling systems EXEM BWR-2000 Methodology.

Only heatup (HUXY) is analyzed for the reload specific neutronic design.

7.5 Neutron 17 STAIF Long term stability solution monitoring system 19 RAMONA5-FA Option III criteria: OPRM setpoints are selected to ensure 20 CASMO-4 / that the SLMCPR is not violated 21 MICROBURN- during the limiting stability event.

22 B2 CRWE criteria: Power dependent MCPR and LHGR 23 operating limits established to 24 meet the fuel failure criteria.

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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 2-13 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 2 COTRANSA2 ATWS overpressurization .

transient without criteria: Maximum vessel scram pressure limit of 1500 psig.

ATWS peak pressure only.

14.5.2.2 Generator trip 2 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 15 RODEX2 failure criteria.

16 RODEX4 14.5.2.2.4 LRNB with EOC- 2 COTRANSA2 Transient criteria: Power RPT-OOS 13 XCOBRA dependent MCPR and LHGR operating limits established to 14 XCOBRA-T meet the fuel failure criteria.

15 RODEX2 16 RODEX4 14.5.2.5 Turbine bypass 2 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 15 RODEX2 16 RODEX4 14.5.2.6 Turbine bypass 2 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 15 RODEX2 16 RODEX4 14.5.3.1 Loss of feedwater 17 CASMO-4 Transient criteria: Power heater (LFWH) 25 /MICROBURN- dependent MCPR and LHGR B2 operating limits established to meet the fuel failure criteria 14.5.4.1 Continuous rod 17 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 17 CASMO-4 Mislocated/misoriented criteria:

misoriented fuel 26 /MICROBURN- Small fraction of 10 CFR 50.67 assembly B2 limits Cycle specific analysis.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis 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 14.5.7.1 Recirculation flow 14 CASMO-4 Transient criteria: Flow control failure - 17 /MICROBURN- dependent MCPR and LHGR increasing flow B2 operating limits established to XCOBRA meet the fuel failure criteria.

14.5.8.1 Feedwater 2 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.

15 RODEX2 16 RODEX4 14.5.8.2 Feedwater 2 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- 15 RODEX2 OOS 16 RODEX4 14.5.8.3 Feedwater 2 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 15 RODEX2 16 RODEX4 14.6.2 Control rod drop 17 CASMO-4 accident (CRDA) /MICROBURN- CRDA criteria: Maximum B2 deposited fuel rod enthalpy is less than 280 cal/g. (The Cycle 19 analysis result is less than 230 cal/g.)

14.6.3 Loss-of-coolant 18 HUXY LOCA criteria: 10 CFR 50.46.

accident (LOCA) EXEM BWR-2000 Methodology.

Only heatup (HUXY) is analyzed for the reload specific neutronic design.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 3-1 3.0 Mechanical Design Analysis Mechanical design exposure limits for ATRIUM 1OXM and ATRIUM-10 fuel are presented in Reference 4, 27, and 28. The maximum exposure limits for the ATRIUM 1OXM and ATRIUM-10 reload fuel are:

54.0 GWd/MTU average assembly exposure 62.0 GWd/MTU rod average exposure (full-length fuel rods)

The fuel cycle design analyses (Reference 1) verified all fuel assemblies remain within licensed burnup limits. The LHGR limits are presented in Section 8.0.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis 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 5. Analysis results demonstrate the thermal-hydraulic design and compatibility criteria are satisfied for the transition core consisting of ATRIUM 1OXM and ATRIUM-10 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 12. The analysis was performed with a power distribution conservatively representing expected reactor operation throughout the cycle.

SLMCPR analysis used the ACE/ATRIUM 10XM critical power correlation (References 29, 30, and 31) for the ATRIUM 10XM fuel while the SPCB critical power correlation (Reference 32) is used for the ATRIUM-10.

In the AREVA methodology, the effects of channel bow on the critical power performance are accounted for in the SLMCPR analysis. Reference 12 discusses the application of a realistic channel bow model.

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.

Analysis of the Unit 2 Cycle 19 SLMCPR using the methodology in Reference 12 resulted in a value of 1.04 for two-loop operation (TLO) and a value of 1.05 for single-loop operation (SLO) as documented in Reference 8. Analysis results including the SLMCPR and the percentage of rods expected to experience boiling transition are summarized in Table 4.2. The results presented in Table 4.2 reflect the use of conservatively selected SLMCPR values of 1.06 for TLO and 1.08 for SLO.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 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 19. 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.

DIVOM calculations are performed to obtain 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 24. The methodology employs 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

20. Generation of plant-specific DIVOM data is consistent with Reference 21. 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 22. BSP curves have been evaluated using an approved methodology (Reference 23) 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 boundaries based on these endpoints can then be determined using the generic shape generating function from Reference 22. 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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 4-3 Table 4.1 Fuel- and Plant-Related Uncertainties for Safety Limit MCPR Analyses Parameter Uncertainty Fuel-Related Uncertainties I

]

Plant-RelatedUncertainties 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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 4-4 Table 4.2 Results Summary for Safety Limit MCPR Analyses Percentage SLMCPR of Rods in Boiling Transition TLO - 1.06 0.042 SLO - 1.08 0.034 AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 4-5 Table 4.3 OPRM Setpoints OPRM OLMCPR OLMCPR Setpoint (SS) (2PT) 1.05 1.15 1.18 1.06 1.17 1.20 1.07 1.19 1.22 1.08 1.20 1.24 1.09 1.22 1.26 1.10 1.24 1.28 1.11 1.26 1.30 1.12 1.28 1.32 1.13 1.30 1.34 1.14 1.33 1.37 1.15 1.35 1.39 Rated Power Off-Rated OLMCPR as Acceptance OLMCPR described in Criteria at 45% Flow Section 8.0 Section 8.0 AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 4-6 Table 4.4 BSP Endpoints for Browns Ferry Unit 2 Cycle 19 Feedwater Temperature Operation End Point Power Flow Mode Region Designation (%rated) (%rated)

Nominal Scram IA 63.72 42.00 Nominal Scram lB 43.88 29.00 Nominal Controlled IIA 73.46 50.00 entry Nominal Controlled lIB 30.72 29.00 entry FFTR/ Scram IA 65.71 42.00 FHOOS FFTR/ Scram IB 43.88 29.00 FHOOS FFTR/ Controlled IIA 73.46 50.00 FHOOS entry FFTR/ Controlled 1iB 30.72 29.00 FHOOS entry AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis 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 2), XCOBRA-T (Reference 13), XCOBRA (Reference 14), and CASMO-4/MICROBURN-B2 (Reference 17) 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 17). 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 ACE/ATRIUM 1OXM critical power correlation (References 29, 30, and 31) is used to evaluate the thermal margin for the ATRIUM 10XM fuel.

The SPCB critical power correlation (Reference 32) is used to evaluate the thermal margin of the ATRIUM-10 fuel. Fuel pellet-to-cladding gap conductance values are based on RODEX2 (Reference 15) calculations for the BFE2-19 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 Browns Ferry, 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 33 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 29,206.3 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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-2 EFPD (core average exposure of 32,734 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 stea'm 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 FFTRlCoastdown operation to a core average exposure of 34,147.6 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 if the 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 33) 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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis 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 Table 5.3. 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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis 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. Base case limiting TTNB transient analysis results for NSS insertion times and at EOCLB are shown in Table 5.4. Comparison of these results with the results provided in Table 5.3 show that the LRNB event bounds 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 AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-5 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.

FWCF analyses were performed for a range of power/flow conditions to support generation of the thermal limits. Table 5.5 presents 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 100OF 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 25 methodology to determine the change in MCPR for the event. The LFWH results are presented in Table 5.6.

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 5.7 for the analytical unfiltered RBM high power setpoint values of 107% to 117%. At all intermediate and lower power setpoint AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-6 values, the MCPRP values for ATRIUM 1OXM and ATRIUM-10 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 ATRIUM 1OXM and ATRIUM-10 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 5.8, 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 all fuel types in the core. 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 5.9. MCPRf limits providing the required protection are presented in Table 8.3. 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 1OXM and 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.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-7 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 8.6.

The maximum flow during a flow excursion in SLO is much less than the maximum flow during TLO. Therefore, the flow-dependent MCPR limits and LHGR multipliers for TLO are applicable for SLO.

5.3 Equipment Out-of-Service Scenarios The EOOS scenarios supported are shown in Table 1.1. As noted in Table 1.1, base case and each EOOS condition is supported in combination with 1 MSRVOOS, EOC-RPT-OOS, up to 2 TIP machines out-of-service 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.

When EOC-RPT is inoperable, no credit is assumed for RPT 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.

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.

Base thermal limits presented in Section 8.0 are applicable with or without function of the EOC-RPT.

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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-8 5.3.2 FHOOS The FHOOS scenario assumes a feedwater temperature reduction of 65 0 F (55 0 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.

5.3.3 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.

0 Without a turbine trip signal, scram occurs on either high flux or high dome pressure to terminate the event.

Analyses were performed for LRNB events assuming PLUOOS.

5.3.4 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 AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-9 beyond the EOCLB exposure since a FW temperature reduction is included to attain the additional cycle extension to the FFTR/coastdown exposure.

5.3.5 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).

5.3.6 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 FFTRlcoastdown exposure.

5.3.7 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 FW temperature reduction is included to attain the additional cycle extension to the FFTR/coastdown exposure.

5.3.8 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.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-10 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 32,734 MWd/MTU is given in Table 5.10.

Operation is considered to be in compliance when:

The integrated normalized power generated in the bottom 7 nodes from the projected EOFP solution at the state conditions provided in Table 5.10 is greater than the integrated normalized power generated in the bottom 7 nodes in the licensing basis axial power profile, and the individual normalized power from the projected EOFP solution is greater than the corresponding normalized power from the licensing basis axial power profile for at least 6 of the 7 bottom nodes.

The projected EOFP condition occurs at a core average exposure less than or equal to EOCLB.

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 5.10 was calculated using the MICROBURN-B2 code.

Compliance analyses must also be performed using MICROBURN-B2 or POWERPLEX-III*.

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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-11 Table 5.1 Exposure Basis for Transient Analysis Core Average Exposure (MWd/MTU) Comments 17,206.5 Beginning of cycle 29,206.3 Break point for exposure-dependent MCPRP limits (NEOC) 32,734.0 Design basis rod patterns to EOFP + 15 EFPD (EOCLB) 34,147.6 Maximum licensing core exposure - including FFTR

/Coastdown 32,520.4 (17,224.4)* Cycle 18 EOC (nominal value) 31,984.3 (16,688.3)* Cycle 18 EOC (short window) 32,877.7 (17,581.7)* Cycle 18 EOC (long window)

• Corresponding Cycle 18 cycle exposure.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-12 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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-13 Table 5.3 Base Case LRNB Transient Results Power NEOC EOCLB

(% rated) A10XM AT10 AT10 A1OXM AT10 AT10 ACPR ACPR HFR ACPR ACPR HFR TSSS Insertion Times 100 0.29 0.33 1.29 0.31 0.35 1.38 90 0.32 0.34 1.30 0.33 0.37 1.40 75 0.33 0.34 1.29 0.33 0.35 1.38 50 0.75 0.83 1.76 0.75 0.83 1.80 NSS Insertion Times 100 0.26 0.30 1.27 0.30 0.34 1.37 90 0.29 0.32 1.29 0.31 0.35 1.39 75 0.31 0.32 1.28 0.32 0.34 1.37 50 0.75 0.82 1.75 0.75 0.82 1.79 AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-14 Table 5.4 Base Case TTNB Transient Results Power EOCLB

(% rated) A1OXM AT10 AT10 ACPR ACPR HFR NSS Insertion Times 100 0.30 0.33 1.37 90 0.30 0.34 1.37 75 0.30 0.33 1.35 AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-15 Table 5.5 Base Case FWCF Transient Results TSSS Insertion Times 100 0.37 0.39 1.40 0.39 0.39 1.47 90 0.43 0.45 1.47 0.44 0.45 1.53 75 0.52 0.53 1.55 0.52 0.53 1.59 65 0.59 0.60 1.63 0.60 0.60 1.64 60 0.64 0.64 1.67 0.64 0.64 1.67 50 0.77 0.82 1.82 0.77 0.82 1.82 40 0.96 1.10 2.09 0.96 1.10 2.09 30 1.26 1.45 2.37 1.26 1.45 2.37 30 at > 50%F below Pbypass 1.94 2.22 3.33 1.94 2.22 3.33 30 at5<50%F below Pbypass 1.88 2.15 3.13 1.88 2.15 3.13 25 at > 50%F below Pbypass 2.32 2.58 3.78 2.32 2.58 3.78 25 at < 50%F below Pbypass 2.22 2.52 3.51 2.22 2.52 3.51 NSS Insertion Times 100 0.35 0.36 1.37 0.37 0.38 1.46 90 0.41 0.42 1.45 0.43 0.42 1.52 75 0.50 0.51 1.54 0.51 0.51 1.59 65 0.58 0.58 1.61 0.59 0.58 1.64 60 0.62 0.62 1.65 0.63 0.62 1.67 50 0.75 0.77 1.79 0.75 0.77 1.79 40 0.95 1.04 2.06 0.95 1.04 2.06 30 1.22 1.38 2.34 1.22 1.38 2.34 AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-16 Table 5.6 Loss of Feedwater Heating Transient Analysis Results Power

(% rated) ACPR*

100 0.21 90 0.22 80 0.23 70 0.24 60 0.25 50 0.27 40 0.29 30 0.34 25 0.38 Table 5.7 Control Rod Withdrawal Error ACPR Results Analytical RBM Setpoint (without filter) ACPR*

(%)

107 0.11 ill 0.18 114 0.29 117 0.31

• Results are for the most limiting of the ATRIUM 1OXM or ATRIUM-10 fuel in the core.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-17 Table 5.8 RBM Operability Requirements Thermal Power Applicable

(% rated) MCPR 1.76 TLO

Ž!27% and <90% 1'.80 SLO

_>90% 1.39 TLO Table 5.9 Flow-Dependent MCPR Results Core Flow ATRIUM 1OXM ATRIUM-10

(% rated) Limiting MCPR Limiting MCPR 30 1.43 1.48 40 1.35 1.38 50 1.34 1.35 60 1.33 1.32 70 1.29 1.27 80 1.21 1.23 90 1.18 1.19 100 1.14 1.15 107 1.06 1.06 AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-18 Table 5.10 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 Core average exposure 32,734 (EOCLB), MWd/MTU Licensing Axial Power Profile (Normalized)

Node Power Top 25 0.242 24 0.694 23 0.898 22 1.029 21 1.102 20 1.165 19 1.223 18 1.287 17 1.335 16 1.460 15 1.502 14 1.478 13 1.520 12 1.477 11 1.397 10 1.298 9 1.190 8 1.048 7 0.886 6 0.746 5 0.615 4 0.512 3 0.441 2 0.353 Bottom 1 0.103 Sum of Bottom 7 Nodes = 3.656 AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-19 V

4-0 4-.

Figure 5.1 EOCLB LRNB at 1OOP/105F - TSSS Key Parameters AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-20 0

N C

0 E

L U

C

)

0

-C)

t (D

3.0 6.0 Time (seconds)

Figure 5.2 EOCLB LRNB at 100P/1 05F - TSSS Sensed Water Level AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-21 a)

L-a.

.0 1.0 2.0 3.0 4.0 5.0 6.0 Time (seconds)

Figure 5.3 EOCLB LRNB at 1OOP/105F - TSSS Vessel Pressures AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-22 Relative Core Power Relative Heat Flux Relative Total Core Flow Relative Steam Flow 300.0-Relative Feed Flow 200.0-4-- -- --

0 -- -- -- -- -- -- -- --

(D- -- -- -- -1.

100.0-I)

.0-1/

-n1 nflA 0 2.5 5.0 7.5 10.0 12.5 15.0 17.5 20.0 Time (seconds)

Figure 5.4 EOCLB FWCF at 10OP/105F - TSSS Key Parameters AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-23 70.0 L._

0 N

. 60.0-E

.4-,

CL 30.0-42 0.0-240.0-t-J 2 0.0

.0 2.6 5.0 7.5 10.0 12.5 15.0 17.5 20.0 Time (seconds)

Figure 5.5 EOCLB FWCF at 100P/1 05F - TSSS Sensed Water Level AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 5-24 1300.0 Vessel Lower Plenum Steam Dome 1250.0-

/

/

1200.0-W I It U) 1150.0-I 1100.0-II'I 1050.0-1000.0

.0 2.5 6.0 7.5 10.0 12.5 15.0 17.5 20.0 Time (seconds)

Figure 5.6 EOCLB FWCF at 1OOP/105F - TSSS Vessel Pressures AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 6-1 6.0 Postulated Accidents 6.1 Loss-of-Coolant-Accident (LOCA)

The results of the ATRIUM 1OXM LOCA analysis are presented in References 6 and 7. The ATRIUM 1OXM PCT is 1903 0 F. The peak local metal water reaction is 1.16% and the maximum core wide metal-water reaction (for hydrogen generation) for a full ATRIUM 1OXM core is

<1.0%.

Thermal-hydraulic characteristics of the ATRIUM-10 and ATRIUM 1OXM fuel designs are similar as presented in Reference 5. Therefore, the core response during a LOCA will not be significantly different for a full core of ATRIUM-10 fuel or a mixed core of ATRIUM-10 and ATRIUM 1OXM 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. Reference 34 results for ATRIUM-10 LOCA remain applicable.

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.

6.2 Control Rod 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 36. Subsequent calculations have shown the methodology is applicable to fuel modeled with the CASMO-4/MICROBURN-B2 code system and is applicable to ATRIUM-10 and ATRIUM 1OXM fuel.

Maximum deposited fuel rod enthalpy is less than both the current core coolability limit of 280 cal/g and the 230 cal/g limit identified in Standard Review Plan 4.2, Revision 3, Appendix B, Section C, Item 1. Fuel rods conservatively estimated to exceed the existing fuel damage threshold of 170 cal/g are within the UFSAR basis (850 rods). The CRDA analysis results are summarized below.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 6-2 Maximum dropped control rod worth, mk 9.37 Core average Doppler coefficient, Ak/k/F -10.0 x 10-6 Effective delayed neutron fraction 0.0053 Four-bundle local peaking factor 1.467 Maximum deposited fuel rod enthalpy, cal/g 170.7 Maximum number of rods exceeding 170 cal/g 91 6.3 Fuel and Equipment HandlingAccident The fuel handling accident radiological analysis implementing the alternate source term (AST) as approved in Reference 11 was performed with consideration of ATRIUM-1 0 core source terms. The ATRIUM 1OXM source terms have been dispositioned relative to those in the AST analysis of record and found to support the same conclusions. Fuel assembly and reactor core isotopic inventories used as input to design basis radiological accident analyses are applicable to all three units (Reference 11).The number of failed fuel rods for the ATRIUM-10 fuel as previously provided to TVA in Reference 37 for use in the AST analysis is unchanged. The number of failed fuel rods for the ATRIUM 1OXM fuel is 163, which remains bounded by the analysis of record. No other aspect of utilizing the ATRIUM-10 and ATRIUM 1OXM fuel affects the current analysis; therefore, the AST analysis remains applicable.

6.4 Fuel Loading Error(InfrequentEvent)

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 26, 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 fuel mislocation error analysis for Browns Ferry Unit 2 Cycle 19. The analysis evaluated 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 AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 6-3 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 fuel assembly misorientation analysis for the ATRIUM 10XM fuel assemblies in Browns Ferry Unit 2 Cycle 19. The analysis was performed assuming that the limiting assembly was loaded in the worst orientation (rotated 1800), and depleted through the cycle without operator interaction. AREVA has also performed a bounding fuel assembly misorientation analysis for 10 x 10 fuel monitored with the SPCB critical power correlation.

These analyses demonstrate that the small fraction of 10 CFR 50.67 offsite dose criteria is conservatively satisfied. A dose consequence evaluation is not necessary since no rod 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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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis 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 2) 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.

• 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 1336 psig occurs in the lower plenum. The maximum dome pressure for the same event is 1301 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 38. Margin to the pressure limits shown in AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 7-2 Table 7.1 are more than adequate to compensate for NRC concerns related to Doppler-effects and exposure-dependent thermal conductivity degradation.

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 132.6% of rated steam flow) allowing a maximum TCV flow of 106.1 % 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 1399 psig and the maximum dome pressure is 1379 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 38. Margin to the pressure limits shown in Table 7.2 are more than adequate to compensate for NRC concerns related to Doppler-effects and exposure-dependent thermal conductivity degradation.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 7-3 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.

[I 7.3 Standby Liquid ControlSystem 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 2 SLC system is required to be able to inject 660 ppm natural boron equivalent at 70°F into the reactor coolant. AREVA has performed an analysis demonstrating the SLC system AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 7-4 meets the required shutdown capability for the cycle. The analysis was performed at a coolant temperature of 3661F, with a boron concentration equivalent to 660 ppm at 680 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 1.65%

Alk/k based on the Cycle 18 EOC short window, which is the most limiting exposure bound by the short and long Cycle 18 exposure window.

7.4 Fuel Criticality The spent fuel pool criticality analysis for ATRIUM-10 and ATRIUM 1OXM fuel are presented in References 9 and 35, respectively. The ATRIUM-10 and ATRIUM-10 XM fuel assemblies identified for the cycle meet the spent fuel storage requirements. ATRIUM-10 and ATRIUM 1OXM fuel assemblies will not be stored in the new fuel storage vault.

• TVA Browns Ferry SLC licensing basis documents indicate a minimum of 660 ppm boron at a temperature of 70'F. The AREVA cold analysis basis of 680 F represents a negligible difference and the results are adequate to protect the 70°F licensing basis for the plant.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis 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 272 127 1336 1301 (102P/1 05F)

TSV closure without bypass 454 135 1329 1291 (102P/105F)

TCV closure without bypass 454 135 1330 1291 (102P/1 05F)

Pressure Limit 1375 1325 Limit

• Pressure results include a 7-psi increase to bound a bias in the void-quality correlations (Reference 38).

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis 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 251 139 1377 1355 (1OOP/1 05F)

MSIV closure 271 136 1390 1370 (100P/81F)

PRFO 260 151 1384 1362 (1OOP/1 05F)

PRFO 236 143 1399 1379 (100P/81 F)

Pressure Limt -1500 1500 Limit

• Pressure results include a 10-psi increase to bound a bias in the void-quality correlations (Reference 38).

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 7-7 Table 7.3 [

I

• [ I tr I

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 7-8 0

4-0)

C.)

C:

0) a-6.0 Time (seconds)

Figure 7.1 MSIV Closure Overpressurization Event at 102P/105F - Key Parameters AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 7-9 0

N E

0 4-1 0

a--

Cl)

.0 2.0 4.0 6.0 8.0 10.0 12.0 Time (seconds)

Figure 7.2 MSIV Closure Overpressurization Event at 102P/105F - Sensed Water Level AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 7-10 a

a-G)

Cl)

Co ID L

a-Figure 7.3 MSIV Closure Overpressurization Event at 102P/1 05F - Vessel Pressures AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 7-11 IN, E

ILL E

a Cl)

Time (seconds)

Figure 7.4 MSIV Closure Overpressurization Event at 102P1/105F - Safety/Relief Valve Flow Rates AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 7-12 0

W4 0

20.0 30.0 Time (seconds)

Figure 7.5 PRFO ATWS Overpressurization Event at IOOP/81F - Key Parameters AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 7-13 0

o N

E L.

. C..

b0 Figure 7.6 PRFO ATWS Overpressurization Event at 1OOP/81 F - Sensed Water Level AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 7-14 0

Co 0~

Co tD Ca CO

'I)

L 0~

Figure 7.7 PRFO ATWS.Overpressurization Event at 100P/81 F - Vessel Pressures AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 7-15 IMoao*

Low Setpt (3)

M!g elp~ 414 -

_H -Setpt_(5)

High IS .(5) ----

1250.0-aI)

E

-~

- 4.,A~

.a

> 750.0-E 500.0-a1)

(n C

250.0-

.0

.0 10.0 20.0 30.0 40.0 50.0 Time (seconds)

Figure 7.8 PRFO ATWS Overpressurization Event at 10OP/81F - Safety/Relief Valve Flow Rates AREVA NP Inc.

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Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis 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 TLO SLMCPR of 1.06 and a SLO SLMCPR of 1.08. 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 FFTR/Coastdown. MCPR limits are established to support base case operation and the EOOS scenarios presented in Table 1.1.

TLO MCPRP limits for ATRIUM 1OXM and ATRIUM-10 fuel are presented for NSS (Table 8. 1) and TSSS (Table 8.2) insertion times for the exposure ranges considered. MCPRP limits for SLO are 0.02 higher for all cases. Comparisons of the limiting AOT analysis results and the MCPRP limits for ATRIUM 1OXM and ATRIUM-10 fuel are presented in Appendix A.

MCPRf limits protect against fuel failures during a postulated slow flow excursion. ATRIUM 1OXM and ATRIUM-10 fuel limits are presented in Table 8.3 and are applicable for all cycle exposures and EOOS conditions identified in Table 1.1.

8.2 LHGR Limits The LHGR limits for ATRIUM 10XM and ATRIUM-10 fuel are presented in Table 8.4. 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.

The ATRIUM 1OXM LHGRFACp multipliers are determined using the RODEX4 thermal-mechanical methodology (Reference 16). The ATRIUM-10 LHGRFACP multipliers are determined using the heat flux ratio results from the transient analyses.

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 Table 8.5 for both ATRIUM 1OXM and ATRIUM-10 fuel. Comparisons of the limiting results and the LHGRFACP limits are presented in Appendix A.

AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 8-2 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 8.6 for both ATRIUM 1OXM and ATRIUM-10 fuel. LHGRFACf multipliers are applicable for all cycle exposures and EOOS conditions identified in Table 1.1.

8.3 MAPLHGR Limits ATRIUM 1OXM and ATRIUM-10 MAPLHGR limits are discussed in References 7 and 34, respectively. The TLO limits for ATRIUM 1OXM and ATRIUM-10 fuel are presented in Table 8.7.

For SLO, a multiplier of 0.85 must be applied to the TLO MAPLHGR limits of both fuel designs.

Power and flow dependent MAPFAC setdowns are not required; therefore, MAPFAC=1.0.

AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 8-3 Table 8.1 MCPRp Limits for NSS Insertion Times*

BOC to BOC to BOC to Operating Power NEOC EOCLB End of COAST Condition (% of rated) A10XM AT10 A10XM AT10 A10XM AT10 100.0 1.41 1.46 1.43 1.48 1.47 1.51 75.0 1.56 1.60 1.58 1.60 1.61 1.65 65.0 1.64 1.67 1.65 1.67 1.70 1.73 50.0 --- 1.86 --- 1.86 ......

50.0 1.81 1.91 1.81 1.91 1.88 1.96 Baecase 40.0 2.01 2.13 2.01 2.13 2.10 2.27 operation 30.0 2.28 2.47 2.28 2.47 2.40 2.62

.30.0 at > 50%F 3.00 3.31 3.00 3.31 3.12 3.48 25.0 at > 50%F 3.38 3.67 3.38 3.67 3.53 3.92 30.0 at < 50%F 2.94 3.24 2.94 3.24 3.06 3.50 25.0 at < 50%F 3.28 3.61 3.28 3.61 3.44 3.90 100.0 1.44 1.51 1.46 1.53 1.49 1.56 75.0 1.59 1.65 1.61 1.66 1.64 1.70 65.0 1.67 1.72 1.68 1.73 1.73 1.78 50.0 .... 1.87 --- 1.87 ......

50.0 1.84 1.91 1.84 1.91 1.90 1.96 TBVOOS 40.0 2.04 2.13 2.04 2.13 2.13 2.27 30.0 2.29 2.47 2.29 2.47 2.41 2.62 30.0 at > 50%F 3.44 3.74 3.44 3.74 3.62 3.96 25.0 at > 50%F 4.02 4.28 4.02 4.28 4.21 4.57 30.0 at5<50%F 2.97 3.24 2.97 3.24 3.16 3.50 25.0 at < 50%F 3.52 3.77 3.52 3.77 3.76 4.00 10 0 .0 1.4 4 1.49 1.47 1.5 1 ......

7 5 .0 1.6 1 1.6 4 1.6 1 1.6 5 ......

6 5 .0 1.6 9 1.7 3 1.7 0 1.7 3 ......

50.0 ---.---...........

50.0 1.88 1.96 1.88 1.96 ......

FHOOS 40.0 2.10 2.27 2.10 2.27 ......

30.0 2.40 2.62 2.40 2.62 30.0 at > 50%F 3.12 3.48 3.12 3.48 ---

25.0 at > 50%F 3.53 3.92 3.53 3.92 ......

30.0 at < 50%F 3.06 3.50 3.06 3.50 ......

25.0 at 5 50%F 3.44 3.90 3.44 3.90 100.0 1.41 1.46 1.43 1.48 1.47 1.51 75.0 1.56 1.60 1.58 1.60 1.61 1.65 65.0 1.71 1.82 1.72 1.84 1.73 1.84 50 .0 ---.-.-.--.---.---..-

50.0 1.81 1.91 1.81 1.91 1.88 1.96 PLUOOS 40.0 2.01 2.13 2.01 2.13 2.10 2.27 30.0 2.28 2.47 2.28 2.47 2.40 2.62 30.0 at > 50%F 3.00 3.31 3.00 3.31 3.12 3.48 25.0 at > 50%F 3.38 3.67 3.38 3.67 3.53 3.92 30.0 at < 50%F 2.94 3.24 2.94 3.24 3.06 3.50 25.0 at 5 50%F 3.28 3.61 3.28 3.61 3.44 3.90 Limits support operation with or without EOC-RPT-OOS and 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.

BOC to End of COAST limits also support operation with FFTR/FHOOS which bounds operation with feedwater heaters in-service. SLO MCPRp limits will be 0.02 higher.

AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 8-4 Table 8.1 MCPRP Limits for NSS Insertion Times (Continued)

BOC to BOC to BOC to Operating Power NEOC EOCLB End of COAST Condition (% of rated) A1OXM AT10 A1OXM AT10 A10XM AT10 100.0 1.46 1.53 1.49 1.56 ..

75.0 1.64 1.69 1.64 1.70 65.0 1.72 1.77 1.73 1.78 ..

5 0 .0 ---........ ....

50.0 1.90 1.96 1.90 1.96 ..

aBVOOS 40.0 2.13 2.27 2.13 2.27 ....

30.0 2.41 2.62 2.41 2.62 ....

30.0 at > 50%F 3.62 3.96 3.62 3.96 ---

25.0 at > 50%F 4.21 4.57 4.21 4.57 .

30.0 at < 50%F 3.16 3.50 3.16 3.50 ......

25.0 at < 50%F 3.76 4.00 3.76 4.00 ......

100.0 1.44 1.51 1.46 1.53 1.49 1.56 75.0 1.59 1.65 1.61 1.66 1.64 1.70 65.0 1.71 1.82 1.72 1.84 1.73 1.84 5 0 .0 ---.....---.......

50.0 1.84 1.91 1.84 1.91 1.90 1.96 aBVOOS 40.0 2.04 2.13 2.04 2.13 2.13 2.27 30.0 2.29 2.47 2.29 2.47 2.41 2.62 30.0 at > 50%F 3.44 3.74 3.44 3.74 3.62 3.96 25.0 at > 50%F 4.02 4.28 4.02 4.28 4.21 4.57 30.0 at < 50%F 2.97 3.24 2.97 3.24 3.16 3.50 25.0 at < 50%F 3.52 3.77 3.52 3.77 3.76 4.00 10 0 .0 1.4 4 1.49 1.4 7 1.5 1 ......

7 5 .0 1.6 1 1.6 4 1.6 1 1.6 5 ......

6 5 .0 1.7 1 1.8 2 1.7 2 1.8 4 ......

5 0 .0 ---..--.--.....

50.0 1.88 1.96 1.88 1.96 ---

aH OOS 40.0 2.10 2.27 2.10 2.27 30.0 2.40 2.62 2.40 2.62 ......

30.0 at > 50%F 3.12 3.48 3.12 3.48 ......

25.0 at > 50%F 3.53 3.92 3.53 3.92 ......

30.0 at < 50%F 3.06 3.50 3.06 3.50 ---

25.0 at < 50%F 3.44 3.90 3.44 3.90 10 0 .0 1.46 1.5 3 1.49 1.5 6 ......

7 5 .0 1.6 4 1.6 9 1.6 4 1.7 0 ......

6 5 .0 1.7 2 1.8 2 1.7 3 1.84 ......

50.0 ..................

TBVOOS, 50.0 1.90 1.96 1.90 1.96 ......

FHOOS, 40.0 2.13 2.27 2.13 2.27 ---

and PLUOOS 30.0 2.41 2.62 2.41 2.62 ......

30.0 at > 50%F 3.62 3.96 3.62 3.96 ---...

25.0 at > 50%F 4.21 4.57 4.21 4.57 ......

30.0 at-< 50%F 3.16 3.50 3.16 3.50 ......

25.0 at < 50%F 3.76 4.00 3.76 4.00 AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 8-5 Table 8.2 MCPRp Limits for TSSS Insertion Times*

BOC to BOC to BOC to Operating Power NEOC EOCLB End of COAST Condition (% of rated) A10XM AT10 A10XM AT10 A10XM AT10 100.0 1.43 1.49 1.45 1.50 1.48 1.53 75.0 1.58 1.62 1.58 1.62 1.63 1.66 65.0 1.65 1.69 1.66 1.69 1.71 1.75

• 50.0 --- 1.91 --- 1.91 ......

50.0 1.83 1.92 1.83 1.92 1.89 2.01 Baecase 40.0 2.02 2.19 2.02 2.19 2.13 2.33 operation 30.0 2.32 2.54 2.32 2.54 2.45 2.70 30.0 at > 50%F 3.00 3.31 3.00 3.31 3.12 3.48 25.0 at > 50%F 3.38 3.67 3.38 3.67 3.53 3.92 30.0 at < 50%F 2.94 3.24 2.94 3.24 3.06 3.50 25.0 at < 50%F 3.28 3.61 3.28 3.61 3.44 3.90 100.0 1.47 1.54 1.48 1.55 1.51 1.58 75.0 1.61 1.67 1.63 1.67 1.66 1.71 65.0 1.69 1.74 1.69 1.75 1.74 1.79 5 0 .0 ---.-.-.--.---.---..-

50.0 1.85 1.92 1.85 1.92 1.92 2.02 TBVOOS 40.0 2.06 2.20 2.06 2.20 2.15 2.33 30.0 2.32 2.54 2.32 2.54 2.45 2.70 30.0 at > 50%F 3.44 3.74 3.44 3.74 3.62 3.96 25.0 at > 50%F 4.02 4.28 4.02 4.28 4.21 4.57 30.0 at5<50%F 2.97 3.24 2.97 3.24 3.16 3.50 25.0 at < 50%F 3.52 3.77 3.52 3.77 3.76 4.00 100.0 1.46 1.51 1.48 1.53 ---

75.0 1.62 1.66 1.63 1.66 65.0 1.71 1.75 1.71 1.75 50.0 --- ---.....

50.0 1.89 2.01 1.89 2.01 ---

FHOOS 40.0 2.13 2.33 2.13 2.33 ---

30.0 2.45 2.70 2.45 2.70 30.0 at > 50%F 3.12 3.48 3.12 3.48 25.0 at > 50%F 3.53 3.92 3.53 3.92 30.0 at : 50%F 3.06 3.50 3.06 3.50 25.0 at < 50%F 3.44 3.90 3.44 3.90 100.0 1.43 1.49 1.45 1.50 1.48 1.53 75.0 1.58 1.62 1.58 1.62 1.63 1.66 65.0 1.72 1.83 1.73 1.86 1.75 1.86 5 0 .0 ---.-.-.--.---.---..-

50.0 1.83 1.92 1.83 1.92 1.89 2.01 PLUOOS 40.0 2.02 2.19 2.02 2.19 2.13 2.33 30.0 2.32 2.54 2.32 2.54 2.45 2.70 30.0 at > 50%F 3.00 3.31 3.00 3.31 3.12 3.48 25.0 at > 50%F 3.38 3.67 3.38 3.67 3.53 3.92 30.0 at < 50%F 2.94 3.24 2.94 3.24 3.06 3.50 25.0 at < 50%F 3.28 3.61 3.28 3.61 3.44 3.90 Limits support operation with or without EOC-RPT-OOS and 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.

BOC to End of COAST limits also support operation with FFTR/FHOOS which bounds operation with feedwater heaters in-service. SLO MCPRP limits will be 0.02 higher.

AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 8-6 Table 8.2 MCPRp Limits for TSSS Insertion Times (Continued)

BOC to BOC to BOC to Operating Power NEOC EOCLB End of COAST Condition (% of rated) A10XM AT10 A1OXM AT10 A10XM AT10 10 0 .0 1.4 9 1.5 6 1.5 1 1.58 ......

7 5 .0 1.6 5 1.7 1 1.6 6 1.71 ......

65.0 1.74 1.79 1.74 1.79 ..

50.0 --- ---.... ....

50.0 1.92 2.02 1.92 2.02 ..

TBVOOS 40.0 2.15 2.33 2.15 2.33 ......

30.0 2.45 2.70 2.45 2.70 ......

30.0 at > 50%F 3.62 3.96 3.62 3.96 ......

25.0 at > 50%F 4.21 4.57 4.21 4.57 ......

30.0 at 5 50%F 3.16 3.50 3.16 3.50 ..

25.0 at < 50%F 3.76 4.00 3.76 4.00 100.0 1.47 1.54 1.48 1.55 1.51 1.58 75.0 1.61 1.67 1.63 1.67 1.66 1.71 65.0 1.72 1.83 1.73 1.86 1.75 1.86 50 .0 .................. --

50.0 1.85 1.92 1.85 1.92 1.92 2.02 TdVOOS 40.0 2.06 2.20 2.06 2.20 2.15 2.33 30.0 2.32 2.54 2.32 2.54 2.45 2.70 30.0 at > 50%F 3.44 3.74 3.44 3.74 3.62 3.96 25.0 at > 50%F 4.02 4.28 4.02 4.28 4.21 4.57 30.0 at - 50%F 2.97 3.24 2.97 3.24 3.16 3.50 25.0 at < 50%F 3.52 3.77 3.52 3.77 3.76 4.00 10 0 .0 1.46 1.5 1 1.48 1.5 3 ......

7 5 .0 1.6 2 1.6 6 1.6 3 1.6 6 ......

65.0 1.72 1.83 1.73 1.86 ..

50.0 --- ---...........

50.0 1.89 2.01 1.89 2.01 ......

aH OOS 40.0 2.13 2.33 2.13 2.33 ......

30.0 2.45 2.70 2.45 2.70 ......

30.0 at > 50%F 3.12 3.48 3.12 3.48 ......

25.0 at > 50%F 3.53 3.92 3.53 3.92 ......

30.0 at < 50%F 3.06 3.50 3.06 3.50 ......

25.0 at < 50%F 3.44 3.90 3.44 3.90 100.0 1.49 1.56 1.51 1.58 7 5 .0 1.6 5 1.7 1 1.6 6 1.7 1 ......

6 5 .0 1.7 4 1.8 3 1.7 4 1.8 6 ......

50 .0 ---.--- ---....

TBVOOS, 50.0 1.92 2.02 1.92 2.02 ......

FHOOS, 40.0 2.15 2.33 2.15 2.33 ..

and PLUOOS 30.0 2.45 2.70 2.45 2.70 ---...

30.0 at > 50%F 3.62 3.96 3.62 3.96 ---...

25.0 at > 50%F 4.21 4.57 4.21 4.57 ......

30.0 at < 50%F 3.16 3.50 3.16 3.50 ......

25.0 at s 50%F 3.76 4.00 3.76 4.00 AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 8-7 Table 8.3 Flow-Dependent MCPR Limits ATRIUM 1OXM and ATRIUM-10 Fuel Core Flow

(% of rated) MCPRf 30.0 1.61 78.0 1.28 107.0 1.28 Table 8.4 Steady-State LHGR Limits Peak ATRIUM 1OXM ATRIUM-10 Pellet Exposure LHGR LHGR (GWd/MTU) (kW/ft) (kW/ft) 0.0 14.1 13.4 18.9 14.1 13.4 74.4 7.4 7.1 AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 8-8 Table 8.5 LHGRFACp Multipliers*

EOOS Power ATRIUM 1OXM ATRIUM-10 Condition (% rated) LHGRFACp LHGRFACp 100.0 1.00 1.00 Base 30.0 0.60 0.52 case 30.0 at > 50%F 0.32 0.38 operation 25.0 at > 50%F 0.28 0.33 TBVIS) 30.0 at -<50%F 0.36 0.40 25.0 at < 50%F 0.30 0.36 100.0 1.00 0.95 30.0 0.58 0.52 TBVOOS1 30.0 at > 50%F 0.32 0.34 25.0 at > 50%F 0.27 0.29 30.0 at - 50%F 0.36 0.40 25.0 at < 50%F 0.30 0.36

• Limits support operation with or without EOC-RPT-OOS and 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-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 8-9 Table 8.6 LHGRFACf Multipliers Core Flow ATRIUM 1OXM ATRIUM-10

(% of rated) LHGRFACf LHGRFACf 0.0 0.66 0.93 30.0 0.66 0.93 44.2 --- 1.00 73.0 1.00 107.0 1.00 1.00 Table 8.7 MAPLHGR Limits Average Planar ATRIUM 1OXM ATRIUM-10 Exposure MAPLHGR MAPLHGR (GWd/MTU) (kW/ft) (kW/ft) 0.0 13.0 12.5 15.0 13.0 12.5 67.0 7.6 7.3 AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 9-1 9.0 References

1. ANP-3145(P) Revision 0, Browns Ferry Unit 2 Cycle 19 LAR Fuel Cycle Design, AREVA NP, August 2012.

2. ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Programfor Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.

3. 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.

4. ANP-3150(P) Revision 0, Mechanical Design Report for Browns FerryATRIUM IOXM Fuel Assemblies, AREVA NP, October 2012.

5. ANP-3082(P) Revision 1, Browns Ferry Thermal-HydraulicDesign Report for A TRIUM TM IOXM Fuel Assemblies, AREVA NP, August 2012.

6. ANP-3152(P) Revision 0, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis for A TRIUMTM IOXM Fuel, AREVA NP, October 2012.

7. ANP-3153(P) Revision 0, Browns Ferry Units 1, 2, and 3 LOCA-ECCS Analysis MAPLHGR Limit for A TRIUM TM IOXM Fuel, AREVA NP, October 2012.

8. 51-9191258-001, "Browns Ferry Unit 2 Cycle 19 MCPR Safety Limit Analysis with SAFLIM3D Methodology," AREVA NP, October 31, 2012.

9. EMF-2939(P) Revision 0, Browns Ferry Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for A TRIUM TM-1O Fuel, Framatome ANP, August 2003.

10. 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.

11. 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, MC01 56, MC0157 and MC01 58)

(TS-405)," September 27, 2004.

12. ANP-1 0307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011.

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-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 9-2

15. 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.

16. BAW-1 0247PA Revision 0, Realistic Thermal-MechanicalFuel Rod Methodology for Boiling Water Reactors, AREVA NP, February 2008.

17. EMF-2158(P)(A) Revision 0, Siemens Power CorporationMethodology for Boiling Water Reactors: Evaluation and Validati6n of CASMO-4/MICROBURN-B2, Siemens Power Corporation, October 1999.

18. EMF-2361 (P)(A), Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP, May 2001.

19. NEDO-32465-A, Licensing Topical Report, Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications, GE Nuclear Energy, August 1996.

20. OG04-0153-260, Plant-Specific Regional Mode DIVOM Procedure Guideline, June 15, 2004.

21. BWROG-03047, Resolution of Reportable Condition for Stability Reload Licensing Calculations Using Generic Regional Mode DIVOM Curve, September 30, 2003.

22. OG02-0119-260, Backup Stability Protection (BSP) for Inoperable Option III Solution, GE Nuclear Energy, July 17, 2002.

23. EMF-CC-074(P)(A) Volume 4 Revision 0, BWR StabilityAnalysis - Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.

24. BAW-1 0255PA Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, AREVA NP, May 2008.

25. AN F-1 358(P)(A) Revision 3, The Loss of FeedwaterHeating Transient in Boiling Water Reactors, Framatome ANP, September 2005.

26. 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.

27. ANP-3159(P) Revision 0, ATRIUM IOXM Fuel Rod Thermal-MechanicalEvaluation for Browns Ferry Unit 2 Cycle 19 Reload BFE2-19, AREVA NP, October 2012.

28. ANP-2939(P) Revision 0, MechanicalDesign Report for Browns Ferry Unit 2 Reload BFE2-17ATRIUM-IC Fuel Assemblies, AREVA NP, July 2010.

29. ANP-1 0298PA Revision 0, ACE/ATRIUM IOXM CriticalPower Correlation,AREVA NP, March 2010.

30. ANP-1 0298PA Revision 0 Supplement 1 P Revision 0, Improved K-factor Model for ACE/ATRIUM IOXM Critical Power Correlation,AREVA NP, December 2011.

AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page 9-3

31. ANP-3140(P) Revision 0, "Browns Ferry Units 1, 2, and 3 Improved K-factor Model for ACE/ATRIUM 10XM Critical Power Correlation," AREVA NP, August 2012.

32. EMF-2209(P)(A) Revision 3, SPCB CriticalPower Correlation,AREVA NP, September 2009.

33. Technical Specification Requirements for Browns Ferry Nuclear Plant Unit 2, Tennessee Valley Authority, as amended.

34. ANP-3016(P) Revision 0, Browns Ferry Units 1, 2, and 3 LOCA-ECCS Analysis MAPLHGR Limit for A TRIUMm- 1O Fuel, AREVA NP, December 2011.

35. ANP-3160(P) Revision 0, Browns Ferry Nuclear Plant Units 1, 2, and 3 Spent Fuel Storage Pool CriticalitySafety Analysis for A TRIUM TM IOXM Fuel, AREVA NP, October 2012.

36. 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.

37. Letter, TA Galioto (FANP) to JF Lemons (TVA), "Fuel Handling Accident Assumptions for Browns Ferry," TAG:02:012, January 23, 2002.

38. ANP-2860(P) Revision 2 Supplement 1P Revision 0, Browns Ferry Unit I - Summary of Responses to Request for Additional Information Extension for ATRIUM IOXM, AREVA NP, November 2012.

AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-1 Appendix A Operating Limits and Results Comparisons The figures and tables presented in this appendix show comparisons of the Browns Ferry Unit 2 Cycle 19 operating limits and the transient analysis results. Comparisons are presented for the ATRIUM 1OXM and ATRIUM-10 MCPRP limits and LHGRFACP multipliers.

AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-2 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 Ej 2.5 2.0 Ao 1.5 o

III

• II I I I 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 1.41 75 1.56 65 1.64 50 ---

50 1.81 40 2.01 30 2.28 30 at > 50%F 3.00 25 at > 50%F 3.38 30 at < 50%F 2.94 25 at < 50%F 3.28 Figure A.1 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - Base Case AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-3 4.0 0 FWCF o LRNB 3.5 A CRWE 3.0 E

ry 2.5 2.0 A0 1.5 A 0 A 0

0 SiII 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 1.46 75 1.60 65 1.67 50 1.86 50 1.91 40 2.13 30 2.47 30 at > 50%F 3.31 25 at > 50%F 3.67 30 at < 50%F 3.24 25 at5<50%F 3.61 Figure A.2 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - Base Case AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-4 4.0 o FWCF 0 LRNB 3.5 A CRWE 3.0 2.5 0

2.0 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 1.43 75 1.58 65 1.65 50 ---

50 1.81 40 2.01 30 2.28 30 at > 50%F 3.00 25 at > 50%F 3.38 30 at:<50%F 2.94 25 at < 50%F 3.28 Figure A.3 BOC to EOCLB MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - Base Case AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-5 4.0 3.5 3.0

t E~ 2.5 ry) 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 1.48 75 1.60 65 1.67 50 1.86 50 1.91 40 2.13 30 2.47 30 at > 50%F 3.31 25 at > 50%F 3.67 30 at < 50%F 3.24 25 at < 50%F 3.61 Figure A.4 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - Base Case AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-6 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 E

-j 2.5 0

2.0 0

1.5 A0 o A 0 0 IIIII 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 1.47 75 1.61 65 1.70 50 ---

50 1.88 40 2.10 30 2.40 30 at > 50%F 3.12 25 at > 50%F 3.53 30 at < 50%F 3.06 25 at < 50%F 3.44 Figure A.5 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM IOXM Fuel - NSS Insertion Times - Base Case AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-7 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 E

2.5 ry 0n 2.0 A

1.5 o 0 A A A 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 75 1.65 65 1.73 50 ---

50 1.96 40 2.27 30 2.62 30 at > 50%F 3.48 25 at > 50%F 3.92 30 at < 50%F 3.50 25 at < 50%F 3.90 Figure A.6 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - Base Case AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-8 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 E

2.5 0~

C-)

2.0 A A 1.5 A A 0 A 6 0

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 1.43 75 1.58 65 1.65 50 ---

50 1.83 40 2.02 30 2.32 30 at > 50%F 3.00 25 at > 50%F 3.38 30 at <50%F 2.94 25 at <50%F 3.28 Figure A.7 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - Base Case AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-9 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 a- 2.5 2.0 0 0 A A A 1.5 A 0]

0 A 2 0 A

II 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 75 1.62 65 1.69 50 1.91 50 1.92 40 2.19 30 2.54 30 at > 50%F 3.31 25 at > 50%F 3.67 30 at < 50%F 3.24 25 at - 50%F 3.61 Figure A.8 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - Base Case AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-10 4.0 o3 FWCF o LRNB 3.5 A CRWE 3.0

._E

_ 2.5 n,

0~

2.0 A

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 1.45 75 1.58 65 1.66 50 ---

50 1.83 40 2.02 30 2.32 30 at > 50%F 3.00 25 at > 50%F 3.38 30 at < 50%F 2.94 25 at < 50%F 3.28 Figure A.9 BOC to EOCLB MCPRP Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - Base Case AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-11 4.0 o FWCF o LRNB 3.5 A CRWE 3.0

J

_ 2.5 A 0 2.0 AA* A A 1.5 A A 0

1.0 I I I 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.50 75 1.62 65 1.69 50 1.91 50 1.92 40 2.19 30 2.54 30 at > 50%F 3.31 25 at > 50%F 3.67 30 at:<50%F 3.24 25 at 5 50%F 3.61 Figure A.10 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - Base Case AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-12 4.0 o FWCF 0 LRNB 3.5 A CRWE 3.0

-J 2.5 C-)

2.0 0

ýA A

1.5 0 A 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 1.48 75 1.63 65 1.71 50 ---

50 1.89 40 2.13 30 2.45 30 at > 50%F 3.12 25 at > 50%F 3.53 30 at < 50%F 3.06 25 at < 50%F 3.44 Figure A.1l BOC to FFTR/Coastdown MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - Base Case AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-13 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 7.

E ry 2.5 2.0 A

1.5 6 o A A A 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 1.53 75 1.66 65 1.75 50 ---

50 2.01 40 2.33 30 2.70 30 at > 50%F 3.48 25 at > 50%F 3.92 30 at:<50%F 3.50 25 at 5 50%F 3.90 Figure A.12 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - Base Case AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-14 5.0 o FWCF o LRNB A CRWE 4.0 1-E

. 3.0 0~

10 2.0 I-A

ýA 0 A 0

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 1.44 75 1.59 65 1.67 50 ---

50 1.84 40 2.04 30 2.29 30 at > 50%F 3.44 25 at > 50%F 4.02 30 at < 50%F 2.97 25 at < 50%F 3.52 Figure A.13 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - TBVOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-15 5.0 o FWCF o LRNB A CRWE 4.0 F

-H E

°--

3.0 02 C-)

2.0 F A

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 75 1.65 65 1.72 50 1.87 50 1.91 40 2.13 30 2.47 30 at > 50%F 3.74 25 at > 50%F 4.28 30 at < 50%F 3.24 25 at 5 50%F 3.77 Figure A.14 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - TBVOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-16 5.0 o FWCF o LRNB A CRWE 4.0

t 3.0 0

3 2.0 0 A 0

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 1.46 75 1.61 65 1.68 50 ---

50 1.84 40 2.04 30 2.29 30 at > 50%F 3.44 25 at > 50%F 4.02 30 at < 50%F 2.97 25 at < 50%F 3.52 Figure A.15 BOC to EOCLB MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - TBVOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-17 5.0 o FWCF

• LRNB

• CRWE 4.0 1-o-

E

-. J

_ 3.0 D3._

2.0 A A A A 2 I0 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 75 1.66 65 1.73 50 1.87 50 1.91 40 2.13 30 2.47 30 at > 50%F 3.74 25 at > 50%F 4.28 30 at:<50%F 3.24 25 at < 50%F 3.77 Figure A.16 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - TBVOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-18 5.0 o FWCF 0 LRNB A CRWE 4.0 1-E r 3.0 0

C-)

2.0 P A 0 A0 A 0 0 0

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 1.49 75 1.64 65 1.73 50 ---

50 1.90 40 2.13 30 2.41 30 at > 50%F 3.62 25 at > 50%F 4.21 30 at5<50%F 3.16 25 at < 50%F 3.76 Figure A.17 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - TBVOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-19 5.0 o FWCF o LRNB A CRWE 4.0 -

E

-j Cý. 3.0 C) 2.0 A

"\0 0 0

0 I 0 1.0 i 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.56 75 1.70 65 1.78 50 ---

50 1.96 40 2.27 30 2.62 30 at > 50%F 3.96 25 at > 50%F 4.57 30 at <50%F 3.50 25 at5<50%F 4.00 Figure A.18 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - TBVOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-20 5.0 o FWCF o LRNB A CRWE 4.0 [-

oE

t

_ 3.0 Of nY 2.0 [-

IIII I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated) 0 Power MCPRp

(% of rated) Limit 100 1.47 75 1.61 65 1.69 50 ---

50 1.85 40 2.06 30 2.32 30 at > 50%F 3.44 25 at > 50%F 4.02 30 at < 50%F 2.97 25 at < 50%F 3.52 Figure A.19 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - TBVOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-21 5.0 o FWCF o LRNB A CRWE 4.0 1-E o--

. 3.0 n,

C-_

0~

2.0 1-0"2 I iiii 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 75 1.67 65 1.74 50 ---

50 1.92 40 2.20 30 2.54 30 at > 50%F 3.74 25 at > 50%F 4.28 30 at5<50%F 3.24 25 at < 50%F 3.77 Figure A.20 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - TBVOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-22 5.0 o FWCF o LRNB A CRWE 4.0 I-E ot C_ 3.0 0::

n-2.0 [-

0 A A

• 0 A O 0 0

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 1.48 75 1.63 65 1.69 50 ---

50 1.85 40 2.06 30 2.32 30 at > 50%F 3.44 25 at > 50%F 4.02 30 at < 50%F 2.97 25 at < 50%F 3.52 Figure A.21 BOC to EOCLB MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - TBVOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-23 5.0 o3 FWCF o LRNB A CRWE 4.0 -

t

_ 3.0 ry 0~

M-_

2.0 F AA00 0

1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.55 75 1.67 65 1.75 50 ---

50 1.92 40 2.20 30 2.54 30 at > 50%F 3.74 25 at > 50%F 4.28 30 at < 50%F 3.24 25 at < 50%F 3.77 Figure A.22 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - TBVOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-24 5.0 o FWCF o LRNB A CRWE 4.0 1-E

. 3.0 Of a-2.0 1-0 0 A 0 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 75 1.66 65 1.74 50 ---

50 1.92 40 2.15 30 2.45 30 at > 50%F 3.62 25 at > 50%F 4.21 30 at5 <50%F 3.16 25 at < 50%F 3.76 Figure A.23 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - TBVOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-25 5.0 o FWCF o LRNB A CRWE 4.0

t E~ 3.0 n) 2.0 I-6 0 0

1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.58 75 1.71 65 1.79 50 ---

50 2.02 40 2.33 30 2.70 30 at > 50%F 3.96 25 at > 50%F 4.57 30 at < 50%F 3.50 25 at < 50%F 4.00 Figure A.24 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - TBVOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-26 4.0 o FWCF o LRNB 3.5 A CRWE 3.0

t E

2.5 n~

2.0 A

A A A 1.5 o

0A A A 0

0 IIIII I I I I I 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 1.44 75 1.61 65 1.69 50 ---

50 1.88 40 2.10 30 2.40 30 at > 50%F 3.12 25 at > 50%F 3.53 30 at < 50%F 3.06 25 at < 50%F 3.44 Figure A.25 BOC to NEOC MCPRp Limits for ATRIUM IOXM Fuel - NSS Insertion Times - FHOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-27 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 E

ry 2.5 0~

2.0 0

[]

1.5 0I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRP

(% of rated) Limit 100 1.49 75 1.64 65 1.73 50 ---

50 1.96 40 2.27 30 2.62 30 at > 50%F 3.48 25 at > 50%F 3.92 30 at < 50%F 3.50 25 at:<50%F 3.90 Figure A.26 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - FHOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-28 4.0 I III o FWCF o LRNB 3.5 A CRWE 3.0

t E~ 2.5 2.0 AAA 1.5 o 6 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 1.47 75 1.61 65 1.70 50 ---

50 1.88 40 2.10 30 2.40 30 at > 50%F 3.12 25 at > 50%F 3.53 30 at 5 50%F 3.06 25 at < 50%F 3.44 Figure A.27 BOC to EOCLB MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - FHOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-29 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 E

2.5 2.0 0 A A 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 1.51 75 1.65 65 1.73 50 ---

50 1.96 40 2.27 30 2.62 30 at > 50%F 3.48 25 at > 50%F 3.92 30 at:<50%F 3.50 25 at < 50%F 3.90 Figure A.28 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - FHOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-30 4.0 03 FWCF 0 LRNB 3.5 A CRWE 3.0

t 2.5 a-)

2.0 0

1.5 0 A 6 0

IIIIII 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 1.46 75 1.62 65 1.71 50 ---

50 1.89 40 2.13 30 2.45 30 at > 50%F 3.12 25 at > 50%F 3.53 30 at < 50%F 3.06 25 at < 50%F 3.44 Figure A.29 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - FHOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-31 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 2.5 0

2.0 0

A A 00 1.5 A [

A 0

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 1.51 75 1.66 65 1.75 50 ---

50 2.01 40 2.33 30 2.70 30 at > 50%F 3.48 25 at > 50%F 3.92 30 at < 50%F 3.50 25 at < 50%F 3.90 Figure A.30 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - FHOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-32 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 E-

_ 2.5 ry 0

2.0 0

1.5 I I I II I 0 IA 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.48 75 1.63 65 1.71 50 ---

50 1.89 40 2.13 30 2.45 30 at > 50%F 3.12 25 at > 50%F 3.53 30 at5<50%F 3.06 25 at < 50%F 3.44 Figure A.31 BOC to EOCLB MCPRp Limits for ATRIUM IOXM Fuel - TSSS Insertion Times - FHOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-33 4.0 o FWCF o LRNB 3.5 S CRWE 3.0

° E c_ 2.5 ry 0

2.0 0

1.5 0 0 0

1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.53 75 1.66 65 1.75 50 ---

50 2.01 40 2.33 30 2.70 30 at > 50%F 3.48 25 at > 50%F 3.92 30 at < 50%F 3.50 25 at 5 50%F 3.90 Figure A.32 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - FHOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-34 4.0 o3 FWCF o LRNB 3.5

• CRWE 3.0

t-E~ 2.5 ry 2.0 A 6 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 1.41 75 1.56 65 1.71 50 ---

50 1.81 40 2.01 30 2.28 30 at > 50%F 3.00 25 at > 50%F 3.38 30 at* 50%F 2.94 25 at < 50%F 3.28 Figure A.33 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - PLUOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-35 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 0__

c~2.5 2.0 0

I II A 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 1.46 75 1.60 65 1.82 50 ---

50 1.91 40 2.13 30 2.47 30 at > 50%F 3.31 25 at > 50%F 3.67 30 at < 50%F 3.24 25 at < 50%F 3.61 Figure A.34 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - PLUOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-36 4.0 o FWCF o LRNB 3.5 A CRWE 3.0

t E~

2.5 2.0 A3 1.5 A 6 A 00 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.43 75 1.58 65 1.72 50 ---

50 1.81 40 2.01 30 2.28 30 at > 50%F 3.00 25 at > 50%F 3.38 30 at < 50%F 2.94 25 at < 50%F 3.28 Figure A.35 BOC to EOCLB MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - PLUOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-37 4.0 o FWCF o LRNB 3.5 A CRWE 3.0

t E~

2.5 2.0 A .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 1.48 75 1.60 65 1.84 50 ---

50 1.91 40 2.13 30 2.47 30 at > 50%F 3.31 25 at > 50%F 3.67 30 at 5 50%F 3.24 25 at < 50%F 3.61 Figure A.36 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - PLUOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-38 4.0 o FWCF 3.5 A CRWE 3.0 E

2.5 f.)

2.0 0

0 1.5 A Q 0 1.0 i i i 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.47 75 1.61 65 1.73 50 ---

50 1.88 40 2.10 30 2.40 30 at > 50%F 3.12 25 at > 50%F 3.53 30 at <50%F 3.06 25 at <50%F 3.44 Figure A.37 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - PLUOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-39 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 2.5 Q-)

2.0 A A 1.5 0

A A 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.51 75 1.65 65 1.84 50 ---

50 1.96 40 2.27 30 2.62 30 at > 50%F 3.48 25 at > 50%F 3.92 30 at < 50%F 3.50 25 at < 50%F 3.90 Figure A.38 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - PLUOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-40 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 E

-j 2.5 2.0 1.5 I6 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRP

(% of rated) Limit 100 1.43 75 1.58 65 1.72 50 ---

50 1.83 40 2.02 30 2.32 30 at > 50%F 3.00 25 at > 50%F 3.38 30 at* 50%F 2.94 25 at < 50%F 3.28 Figure A.39 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - PLUOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-41 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 E

_ 2.5 a_

0 2.0 0

0 A

1.5 A £o 0 18 A A 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.49 75 1.62 65 1.83 50 ---

50 1.92 40 2.19 30 2.54 30 at > 50%F 3.31 25 at > 50%F 3.67 30 at 5 50%F 3.24 25 at < 50%F 3.61 Figure A.40 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - PLUOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-42 4.0 O3 FWCF o LRNB 3.5 A CRWE 3.0

t-E 2.5 n~

0~

M-2.0 1.5 0 0 00 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.45 75 1.58 65 1.73 50 ---

50 1.83 40 2.02 30 2.32 30 at > 50%F 3.00 25 at > 50%F 3.38 30 atS<50%F 2.94 25 at < 50%F 3.28 Figure A.41 BOC to EOCLB MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - PLUOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-43 4.0 o FWCF 0 LRNB 3.5 A CRWE 3.0

t 2.5 C-)

2.0 0

A A A 0 A 1.5 0A 0 8 A A A 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 1.50 75 1.62 65 1.86 50 ---

50 1.92 40 2.19 30 2.54 30 at > 50%F 3.31 25 at > 50%F 3.67 30 at:<50%F 3.24 25 at < 50%F 3.61 Figure A.42 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - PLUOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-44 4.0 D1 FWCF 0 LRNB 3.5 A CRWE 3.0 E

.- I-

. 2.5 0-0 2.0 0

A Ao A A 1.5 SIII 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 1.48 75 1.63 65 1.75 50 ---

50 1.89 40 2.13 30 2.45 30 at > 50%F 3.12 25 at > 50%F 3.53 30 at < 50%F 3.06 25 at < 50%F 3.44 Figure A.43 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - PLUOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-45 4.0 o FWCF o LRNB 3.5

• CRWE 3.0 E

c. 2.5 Cl-2.0 0

,0o A* 0 A 1.5 i ii i i i i0 1.0 0 10 20 30 40 50 60 70 s0 90 100 110 Power (% Rated)

Power MCPRP

(% of rated) Limit 100 1.53 75 1.66 65 1.86 50 ---

50 2.01 40 2.33 30 2.70 30 at > 50%F 3.48 25 at > 50%F 3.92 30 at < 50%F 3.50 25 at < 50%F 3.90 Figure A.44 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - PLUOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-46 5.0 o FWCF o LRNB

• CRWE 4.0

t, E~

3.0 ry 2.0 A0 "0

0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRP

(% of rated) Limit 100 1.46 75 1.64 65 1.72 50 ---

50 1.90 40 2.13 30 2.41 30 at > 50%F 3.62 25 at > 50%F 4.21 30 at:<50%F 3.16 25 at:<50%F 3.76 Figure A.45 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - TBVOOS and FHOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-47 5.0 o FWCF o LRNB

• CRWE 4.0 1-

. 3.0 Of M~

2.0 1-0 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 1.53 75 1.69 65 1.77 50 ---

50 1.96 40 2.27 30 2.62 30 at > 50%F 3.96 25 at > 50%F 4.57 30 at* 50%F 3.50 25 at < 50%F 4.00 Figure A.46 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - TBVOOS and FHOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-48 5.0 0 FWCF 0 LRNB A CRWE 4.0 E

-J 3.0 I-2.0 1-A0 0 6 o A0 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 75 1.64 65 1.73 50 ---

50 1.90 40 2.13 30 2.41 30 at > 50%F 3.62 25 at > 50%F 4.21 30 at:<50%F 3.16 25 at - 50%F 3.76 Figure A.47 BOC to EOCLB MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - TBVOOS and FHOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-49 5.0 o3 FWCF o LRNB A CRWE 4.0 -

t E

°--

o 3.0 ry 03 2.0 1-0\

00 i 0 1.0 I 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.56 75 1.70 65 1.78 50 ---

50 1.96 40 2.27 30 2.62 30 at > 50%F 3.96 25 at > 50%F 4.57 30 at S 50%F 3.50 25 at - 50%F 4.00 Figure A.48 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - TBVOOS and FHOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-50 5.0 o FWCF o LRNB A CRWE 4.0 E

-J 3.0 0-0 2.0 0

0 A 6 6 0

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 1.49 75 1.65 65 1.74 50 ---

50 1.92 40 2.15 30 2.45 30 at > 50%F 3.62 25 at > 50%F 4.21 30 at5<50%F 3.16 25 at < 50%F 3.76 Figure A.49 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - TBVOOS and FHOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-51 5.0 o FWCF o LRNB A CRWE 4.0 k

t E~

3.0 I-n~

2.0 [-

0 0 [

AA 0

fIII 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 75 1.71 65 1.79 50 ---

50 2.02 40 2.33 30 2.70 30 at > 50%F 3.96 25 at > 50%F 4.57 30 at 5 50%F 3.50 25 at < 50%F 4.00 Figure A.50 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - TBVOOS and FHOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-52 5.0 o FWCF o LRNB A CRWE 4.0 k E

o 3.0 n-0_

=

2.0 F I~

0 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 75 1.66 65 1.74 50 ---

50 1.92 40 2.15 30 2.45 30 at > 50%F 3.62 25 at > 50%F 4.21 30 at5-50%F 3.16 25 at: -50%F 3.76 Figure A.51 BOC to EOCLB MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - TBVOOS and FHOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-53 5.0 o FWCF o LRNB A* CRWE 4.0 F 3.0 C-)

2.0 F 0

AA Ao 6 0 0

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 1.58 75 1.71 65 1.79 50 ---

50 2.02 40 2.33 30 2.70 30 at > 50%F 3.96 25 at > 50%F 4.57 30 at 5 50%F 3.50 25 at < 50%F 4.00 Figure A.52 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - TBVOOS and FHOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-54 5.0 o FWCF o LRNB A CRWE 4.0 [

E

. 3.0 rY a_

C) 02 2.0 F 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 1.44 75 1.59 65 1.71 50 ---

50 1.84 40 2.04 30 2.29 30 at > 50%F 3.44 25 at > 50%F 4.02 30 at < 50%F 2.97 25 at < 50%F 3.52 Figure A.53 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - TBVOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-55 5.0 o FWCF o LRNB A CRWE.

4.0 1-

-t -

E

. 3.0 0-2.0 F 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 1.51 75 1.65 65 1.82 50 ---

50 1.91 40 2.13 30 2.47 30 at > 50%F 3.74 25 at > 50%F 4.28 30 at < 50%F 3.24 25 at < 50%F 3.77 Figure A.54 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - TBVOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-56 5.0 o FWCF o LRNB A CRWE 4.0 1-4E o 3.0 0y 0,

\A 2.0 1-0 A A IIII 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 1.46 75 1.61 65 1.72 50 ---

50 1.84 40 2.04 30 2.29 30 at > 50%F 3.44 25 at > 50%F 4.02 30 at < 50%F 2.97 25 at < 50%F 3.52 Figure A.55 BOC to EOCLB MCPRP Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - TBVOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-57 5.0 4.0

_ 3.0 C-y 2.0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.53 75 1.66 65 1.84 50 ---

50 1.91 40 2.13 30 2.47 30 at > 50%F 3.74 25 at > 50%F 4.28 30 at:<50%F 3.24 25 at < 50%F 3.77 Figure A.56 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - TBVOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-58 5.0 o FWCF o LRNB A CRWE 4.0 F E-E

_ 3.0 Of 0..

2.0 F A 0 A

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 1.49 75 1.64 65 1.73 50 ---

50 1.90 40 2.13 30 2.41 30 at > 50%F 3.62 25 at > 50%F 4.21 30 at* 50%F 3.16 25 at < 50%F 3.76 Figure A.57 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - TBVOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-59 5.0 n FWCF o LRNB A CRWE 4.0 p-E

°-I-

. 3.0 (Y

C.)

12.

2.0 1-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 75 1.70 65 1.84 50 ---

50 1.96 40 2.27 30 2.62 30 at > 50%F 3.96 25 at > 50%F 4.57 30 at < 50%F 3.50 25 at < 50%F 4.00 Figure A.58 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - TBVOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-60 5.0 0 FWCF o LRNB A CRWE 4.0 [

E

-j

£)_ 3.0 Of n

2.0 1 A

6 A 0 0 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 1.47 75 1.61 65 1.72 50 ---

50 1.85 40 2.06 30 2.32 30 at > 50%F 3.44 25 at > 50%F 4.02 30 at < 50%F 2.97 25 at < 50%F 3.52 Figure A.59 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - TBVOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-61 5.0 0 FWCF 0 *LRNB A CRWE 4.0

°--,

E

. 3.0 0:

ME) 2.0 1-A 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 75 1.67 65 1.83 50 ---

50 1.92 40 2.20 30 2.54 30 at > 50%F 3.74 25 at > 50%F 4.28 30 at < 50%F 3.24 25 at5-50%F. 3.77 Figure A.60 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - TBVOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-62 5.0 o FWCF o LRNB A CRWE 4.0 1 o--,

E

-j C3 3.0 0~

1-2 2.0 F o

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 1.48 75 1.63 65 1.73 50 ---

50 1.85 40 2.06 30 2.32 30 at > 50%F 3.44 25 at > 50%F 4.02 30 at5<50%F 2.97 25 at < 50%F 3.52 Figure A.61 BOC to EOCLB MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - TBVOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-63 5.0 o3 FWCF o LRNB A CRWE 4.0 F E

3.0 0~

13_

2.0 0 0 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 1.55 75 1.67 65 1.86 50 ---

50 1.92 40 2.20 30 2.54 30 at > 50%F 3.74 25 at > 50%F 4.28 30 at < 50%F 3.24 25 at < 50%F 3.77 Figure A.62 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - TBVOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-64 5.0 o FWCF o LRNB A CRWE 4.0 I

°--,

°E

_ 3.0 Of 2.0 I A

A 0 A Q 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 1.51 75 1.66 65 1.75 50 ---

50 1.92 40 2.15 30 2.45 30 at > 50%F 3.62 25 at > 50%F 4.21 30 at* 50%F 3.16 25 at < 50%F 3.76 Figure A.63 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM IOXM Fuel - TSSS Insertion Times - TBVOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-65 5.0 o FWCF

• LRNB

'% CRWE 4.0 1-

°E 3.0 rY 0~

C-_

2.0 1-0 I I I I 0 0 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.58 75 1.71 65 1.86 50 ---

50 2.02 40 2.33 30 2.70 30 at > 50%F 3.96 25 at > 50%F 4.57 30 at < 50%F 3.50 25 at < 50%F 4.00 Figure A.64 BOC to FFTR/Coastdown MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - TBVOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-66 4.0 o FWCF o LRNB 3.5 A CRWE 3.0

°--

_ 2.5 a-)

2.0 A 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 1.44 75 1.61 65 1.71 50 ---

50 1.88 40 2.10 30 2.40 30 at > 50%F 3.12 25 at > 50%F 3.53 30 at < 50%F 3.06 25 at < 50%F 3.44 Figure A.65 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - FHOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-67 4.0 o FWCF o LRNB 3.5 A CRWE 3.0

t-E ry 2.5 2.0 0

A A2 1.5 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 1.49 75 1.64 65 1.82 50 ---

50 1.96 40 2.27 30 2.62 30 at > 50%F 3.48 25 at > 50%F 3.92 30 at < 50%F 3.50 25 at < 50%F 3.90 Figure A.66 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - FHOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-68 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 E

-j 2.5 0~

ME 2.0 0

A A 1.5 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 1.47 75 1.61 65 1.72 50 50 1.88 40 2.10 30 2.40 30 at > 50%F 3.12 25 at > 50%F 3.53 30 at < 50%F 3.06 25 at < 50%F 3.44 Figure A.67 BOC to EOCLB MCPRp Limits for ATRIUM IOXM Fuel - NSS Insertion Times - FHOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-69 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 E

a- 2.5 0~

M~

2.0 AA 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 75 1.65 65 1.84 50 ---

50 1.96 40 2.27 30 2.62 30 at > 50%F 3.48 25 at > 50%F 3.92 30 at < 50%F 3.50 25 at < 50%F 3.90 Figure A.68 BOC to EOCLB MCPRP Limits for ATRIUM-10 Fuel - NSS Insertion Times - FHOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-70 4.0 o FWCF o LRNB 3.5 A CRWE 3.0

t E. 2.5 0L 2.0 0

A A 1.5 6 A 6 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.46 75 1.62 65 1.72 50 ---

50 1.89 40 2.13 30 2.45 30 at > 50%F 3.12 25 at > 50%F 3.53 30 at < 50%F 3.06 25 at < 50%F 3.44 Figure A.69 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - FHOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-71 4.0 o] FWCF

• o LRNB 3.5 A CRWE 3.0

t E~ 2.5 C) 2.0 0

0 0 1.5 A* A A*

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 1.51 75 1.66 65 1.83 50 ---

50 2.01 40 2.33 30 2.70 30 at > 50%F 3.48 25 at > 50%F 3.92 30 at:<50%F 3.50 25 at < 50%F 3.90 Figure A.70 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - FHOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-72 4.0 o3 FWCF o LRNB 3.5

• CRWE 3.0 E

nj 2.5 2.0 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 1.48 75 1.63 65 1.73 50 ---

50 1.89 40 2.13 30 2.45 30 at > 50%F 3.12 25 at > 50%F 3.53 30 at < 50%F 3.06 25 at < 50%F 3.44 Figure A.71 BOC to EOCLB MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - FHOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-73 4.0 o FWCF o LRNB 3.5 A CRWE 3.0 E

a- 2.5 0~

2.0 A A 1.5 A A A 1.0 i p i i A 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(%of rated) Limit 100 1.53 75 1.66 65 1.86 50 ---

50 2.01 40 2.33 30 2.70 30 at > 50%F 3.48 25 at > 50%F 3.92 30 at < 50%F 3.50 25 at < 50%F 3.90 Figure A.72 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - FHOOS and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-74 5.0 o FWCF o LRNB A CRWE 4.0 I-

°_E

°--

o 3.0 2-0 2.0 [-

A 0 A A Aý 6 A 6 6 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 1.46 75 1.64 65 1.72 50 ---

50 1.90 40 2.13 30 2.41 30 at > 50%F 3.62 25 at > 50%F 4.21 30 at* 50%F 3.16 25 at < 50%F 3.76 Figure A.73 BOC to NEOC MCPRp Limits for ATRIUM IOXM Fuel - NSS Insertion Times - TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-75 5.0 13 FWCF o LRNB A CRWE 4.0 P

t E

-j 0_ 3.0 0_

C-)

M*

2.0 F

,, £ 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.53 75 1.69 65 1.82 50 ---

50 1.96 40 2.27 30 2.62 30 at > 50%F 3.96 25 at > 50%F 4.57 30 at:<50%F 3.50 25 at < 50%F 4.00 Figure A.74 BOC to NEOC MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-76 5.0 o FWCF o LRNB A QRWE 4.0 P F:t E

-j 0_ 3.0 a_

0 2.0 I-A 0 A

AA A 0 o 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 1.49 75 1.64 65 1.73 50 ---

50 1.90 40 2.13 30 2.41 30 at > 50%F 3.62 25 at > 50%F 4.21 30 at:<50%F 3.16 25 at* 50%F 3.76 Figure A.75 BOC to EOCLB MCPRp Limits for ATRIUM 1OXM Fuel - NSS Insertion Times - TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-77 5.0 o FWCF 0 LRNB A CRWE 4.0

t, E~

3.0 ry n

2.0 A A 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 1.56 75 1.70 65 1.84 50 ---

50 1.96 40 2.27 30 2.62 30 at > 50%F 3.96 25 at > 50%F 4.57 30 at < 50%F 3.50 25 at < 50%F 4.00 Figure A.76 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - NSS Insertion Times - TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-78 5.0 o FWCF o LRNB

• CRWE 4.0 1-o--,

°-E

_ 3.0 ry 0~

1_

2.0 1-0 6 A 0 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 1.49 75 1.65 65 1.74 50 ---

50 1.92 40 2.15 30 2.45 30 at > 50%F 3.62 25 at > 50%F 4.21 30 at:<50%F 3.16 25 at < 50%F 3.76 Figure A.77 BOC to NEOC MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-79 5.0 o FWCF o LRNB

• CRWE 4.0 I-Ft E

°-.

Q_ 3.0 rY 0_ \0 2.0 1-A 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 1.56 75 1.71 65 1.83 50 ---

50 2.02 40 2.33 30 2.70 30 at > 50%F 3.96 25 at > 50%F 4.57 30 at5<50%F 3.50 25 at < 50%F 4.00 Figure A.78 BOC to NEOC MCPR. Limits for ATRIUM-10 Fuel - TSSS Insertion Times - TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-80 5.0 o FWCF o LRNB A CRWE 4.0 1-

t

_ 3.0 0-0p 2.0 1-A A o 0-A Q 0 III I I I I I I 1.0 0 10 20 30 40 50 60 70 80 90 1oo 110 Power (% Rated)

Power MCPRp

(% of rated) Limit 100 1.51 75 1.66 65 1.74 50 ---

50 1.92 40 2.15 30 2.45 30 at > 50%F 3.62 25 at > 50%F 4.21 30 at5<50%F 3.16 25 at < 50%F 3.76 Figure A.79 BOC to EOCLB MCPRp Limits for ATRIUM 1OXM Fuel - TSSS Insertion Times - TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-81 5.0 O FWCF o LRNB A CRWE 4.0 F

t-E S3.0 C):

M~

2.0 1-0 A A A A 2~~OA

• A *A 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 1.58 75 1.71 65 1.86 50 50 2.02 40 2.33 30 2.70 30 at > 50%F 3.96 25 at > 50%F 4.57 30 at < 50%F 3.50 25 at < 50%F 4.00 Figure A.80 BOC to EOCLB MCPRp Limits for ATRIUM-10 Fuel - TSSS Insertion Times - TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-82 1.5 o FWCF 1.25 o LRNB 1.0

t C-j

.75 L-J

.5

.25 I I l I I I I I I I

.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power LHGRFACP

(% of rated) Multiplier 100 1.00 30 0.60 30 at > 50%F 0.32 25 at > 50%F 0.28 30 at < 50%F 0.36 25 at <- 50%F 0.30 Figure A.81 All Exposures LHGRFACP Multipliers for ATRIUM 1OXM Fuel - NSSITSSS Insertion Times EOOS with TBVIS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-83 1.5 II o3 FWCF 1.25 o LRNB 1.0

t

.75 L-j

.5

.25 I I I I I I I I I I

.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power LHGRFACP

(% of rated) Multiplier 100 1.00 30 0.52 30 at > 50%F 0.38 25 at > 50%F 0.33 30 at < 50%F 0.40 25 at 5 50%F 0.36 Figure A.82 All Exposures LHGRFACp Multipliers for ATRIUM-10 Fuel - NSS/TSSS Insertion Times EOOS with TBVIS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-84 1.5 o FWCF 1.25

• LRNB 1.0 E

L-J

.75

.5 I II I I II I0

.25

.0 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power LHGRFACP

(% of rated) Multiplier 100 1.00 30 0.58 30 at > 50%F 0.32 25 at > 50%F 0.27 30 at < 50%F 0.36 25 at < 50%F 0.30 Figure A.83 All Exposures LHGRFAC. Multipliers for ATRIUM 1OXM Fuel - NSSrTSSS Insertion Times EOOS with TBVOOS AREVA NP Inc.

ANP-3167(NP)

Revision 0 Browns Ferry Unit 2 Cycle 19 Reload Analysis Page A-85 1.5 o FWCF 1.25 o LRNB 1.0

[] 13 C-) .75 Uj-

.5 i i ii i i0

.25

.0 i 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Power LHGRFACp

(% of rated) Multiplier 100 0.95 30 0.52 30 at > 50%F 0.34 25 at > 50%F 0.29 30 at < 50%F 0.40 25 at < 50%F 0.36 Figure A.84 All Exposures LHGRFACP Multipliers for ATRIUM-10 Fuel - NSS/TSSS Insertion Times EOOS with TBVOOS AREVA NP Inc.